TW462063B - Nuclear reactor cooling apparatus and its operation method - Google Patents

Nuclear reactor cooling apparatus and its operation method Download PDF

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Publication number
TW462063B
TW462063B TW090101750A TW90101750A TW462063B TW 462063 B TW462063 B TW 462063B TW 090101750 A TW090101750 A TW 090101750A TW 90101750 A TW90101750 A TW 90101750A TW 462063 B TW462063 B TW 462063B
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Taiwan
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nuclear reactor
cooling
fuel pool
pipeline
furnace
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TW090101750A
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Chinese (zh)
Inventor
Fumihiko Ishibashi
Takahisa Kondo
Michitomo Kuroda
Takuji Takayama
Minoru Kobayashi
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Toshiba Corp
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    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

The present invention relates to a kind of cooling apparatus for nuclear reactor and its operation method, in which the dosage infected by the radiation for the operators in the nuclear reactor can be reduced when working for the operation in the route of nuclear reactor pressure tank. In addition, the destruction heat can be removed without damaging the fuel assembly body or the operation of exchanging control rod. In the nuclear reactor building, the nuclear reactor well 4 and fuel pool 5 are constructed. The circulating pipeline 17 of fuel pool and the system pipeline 23, 24 of nuclear reactor, which is used to remove the residual heat of the nuclear reactor, for the cooling and cleaning system pipeline 8 are installed at the down-stream side of the pressure adjustment tank 7 adjacent to the gap of the fuel pool 5, in which the outlet side of the fuel pool circulating pipeline 17 is installed inside the nuclear reactor well 4 and the outlet side of the system pipeline 23, 24 for removing the residual heat of the nuclear reactor is installed inside the fuel pool 5. In addition, the radiation covering-layer is contained in the reactor water inside the nuclear reactor pressure tank 1 so as to prevent the radiation from piling up at the bottom portion of the nuclear reactor well 4 and to decrease the dosage infected by the radiation for the operators.

Description

"齋^皆逢讨轰笱員^為費^^-^,·";^ 620 63 A7 7 186pif -doc/ 00 8 B7 五、發明說明(I ) μμμμ. 本發明是關於在核能發電廠中之核反應爐壓力槽內之 通路情況下,不損及作業性、抑制來自核反應爐井的放射 線以降低放射線量以及去除熱衰變之可能性的核反應爐冷 卻設備以及其運轉方法。 發明背景 請參照第16圖所示,以對改良式沸騰水型之核能發 電廠中的核反應爐冷卻設備進行說明。 第16圖所示係爲習知之核反應爐冷卻設備的槪略管 路系統。在第16圖中,符號1係爲已取出上蓋之核反應 爐壓力槽,爐心2上的側板頂蓋係表示移除氣液分離器與 蒸汽乾燥器之狀態。符號3係表示槪略的內泵,在第16 圖中的粗線係表示爐水或池水等的水流狀態,細線則表示 非水流狀態。 在第16圖中,核反應爐壓力槽1,其上端開口部位的 外側面係構築於核反應爐建築物(未圖示)內,且在核反 應爐井4的底部安裝不透水連接材料(未圖示)。核反應 爐壓力槽1之底部利用基座(未圖示)予以支撐。核反應 爐井4與燃料池之間利用池閥6進行區分。 在燃料池5及核反應爐井4中鄰接有多個基底裝置之 間隙調壓槽7。間隙調壓槽7係爲燃料池5及核反應爐井 4內的溢流水的上澄液所流入之空槽,其底部與燃料池冷 卻淨化系統(簡稱爲FPC)管路8相連接。 燃料池冷卻淨化系統管路8依序串連連接有進口停止 4 -----^--------訂·--------線 (請先閱讀背面之沒意事項再填寫本頁) 本紙張尺度適用中國 (CNS)A:I規格⑵0 X 297公釐) 620 6 3 Λ7 7186pif.doc/008 ㈤ 五、發明說明()) 閥9、燃料池冷卻淨化系統泵1〇、燃料池冷卻淨化系統過 濾除氯裝置U、出口停止閥12及燃料池冷卻淨化系統熱 交換器13,燃料池冷卻淨化系統過濾除氯裝置11的上游 側與下游側的出口停止閥12之出口側與具有側管閥14之 燃料池冷卻淨化系統側管管路15相連接。 燃料池冷卻淨化系統泵10、燃料池冷卻淨化系統過濾 除氯裝置11及燃料池冷卻淨化系統熱交換器13各自設有 並列的2相同裝置。燃料池冷卻淨化系統過濾除氯裝置11 與出口停止閥12之間的分歧處連接有抑制池淨化系統(簡 稱爲SPCU)管路16。燃料池冷卻淨化系統熱交換器13 之下游側與燃料池循環管路17相連接,燃料池循環管路17 經由防止逆流閥18與燃料池冷卻淨化系統循環水注入管 路19相連接。 循環水注入管路19設置於燃料池5中,在其下端靠 近燃料池5之池底位置設有循環水注入口。在核反應爐井 4處設有抑制池淨化系統管路16,且與位於燃料池冷卻淨 化系統過濾除氯裝置Π的出口側之抑制池淨化系統管路 16相連接。 在燃料池冷卻淨化系統管路8的進口停止閥9之出口 側與核反應爐井4之間設有含有停止閥21之燃料池冷卻 淨化系統之核反應爐井連接管路22。燃料池冷卻淨化系統 管路8的進口停止閥9之入口側利用具有各自連接於核反 應爐殘留熱去除系統(簡稱爲RHR)管路的核反應爐殘留 熱去除系統之(A)系統管路23與核反應爐殘留熱去除系 5 ί I ^---J I---#·!------^ , (請先間讀背面之注意事項再填寫本頁) 本紙張足度適用中國國家標準<CNS)A4規格<210 X 297公釐) 462063 A7 7 1 8 6pi f . doc / 〇 〇 8 g- 五、發明說明|〔、) 統之(B或c)系統管路24之停止閥27a至27c的燃料池 冷卻淨化系統-核反應爐殘留熱去除系統連接管路28與核 反應爐壓力槽1相連接。 在核反應爐殘留熱去除系統管路中設有第1至第3等 的3系統,在關係的說明上,又區分爲核反應爐殘留熱去 除系統之(A)系統管路23與核反應爐殘留熱去除系統之 (B或C)系統管路24。在核反應爐殘留熱去除系統之(A) 系統管路23與核反應爐殘留熱去除系統之(B或C)系統 管路24中各依序串連連接有核反應爐殘留熱去除系統泵 25與核反應爐殘留熱去除系統熱交換器26,且其下游側 係利用核反應爐殘留熱去除系統-燃料池冷卻淨化系統連 接線路29與燃料池循環管路17相連接。由核反應爐殘留 熱去除系統-燃料池冷卻淨化系統連接線路29所分岐之核 反應爐殘留熱去除系統循環水注入管路在靠近核反應爐井 4內之底部附近設有核反應爐殘留熱去除系統循環水注入 □ 30。 在第16圖中,符號32、33、34a、34b各自表示停止 閥,符號35表示核反應爐給水系統(FDW)。核反應爐 給水系統35係具有第一給水噴霧管路46與第二給水噴霧 管路47,在此之給水噴霧管路46、47各自連接於配設於 核反應爐壓力槽ί內的2個給水噴霧器37、37。 核反應爐殘留熱去除系統之(Α)系統管路23分歧連 接分歧管38,且藉由停止閥39與第一給水噴霧管路46相 連接。又,核反應爐殘留熱去除系統之(Β或C)系統管 6 本紙張尺度適用中國國家標準(CNS)Al規格(210x297公发) (請先閱讀背面之注意事項再填寫本頁) ' 裝 訂---------線 462063 A7 7lS6pif.doc/008 β- 五、發明說明(Ψ) 路24與低壓注水系統(簡稱爲LPFL)噴霧管路相連接, 低壓注水系統噴霧管路45與多個配設於核反應爐壓力槽1 內的低壓注水系統噴霧器36相連接。 在此,核反應爐殘留熱去除系統管路之1系統(核反 應爐殘留熱去除系統之(A)系統)23係與核反應爐給水 系統35之給水噴霧器37相連接,以由此給水噴霧器37 循環至核反應爐壓力槽1中,其他的2系統(核反應爐殘 留熱去除系統之(B或C)系統)24則利用低壓注水系統 噴霧器36循環至核反應爐壓力槽1中。在1系統中有3 個給水噴霧器37,合計2系統中設置有6個’在1系統中 有1個低壓注水系統噴霧器36,合計設置有2個。 在第16圖中符號40表示作業地面高度,符號41表 示冷卻水,符號42表示冷卻水41之液面,符號43表示 設置於核反應爐殘留熱去除系統循環水注入管路31上之 停止閥,符號44表示設置於低壓注水系統管路45上,同 時連接低壓注水系統噴霧器36之停止閥。 發明槪述 核能發電所中所設置之沸騰水型核反應爐其爐心2裝 載了燃料集合體,通入核反應爐壓力槽1內進行控制棒之 交換作業時,基本上,由作業地面高度40開始的作業轉 變爲長膠片之裝置中作業。但,必須要排除核反應爐并4 或燃料池5內的冷卻水流動之影響。 此情形下,在現在的改良式沸騰水型的核反應爐中’ 去除由存在於核反應爐壓力槽1或燃料池5之燃料集合體 7 .衣--------訂---------線 (靖先閱讀背面之注意事項再填寫本頁) 本紙張尺度適用中國國家標準(CNS)A.l規格(210 X 297公釐) 4.620 6 3 7186pif.doc/008 Λ7 Ei7 五、發明說明(?) 內的燃料開始的破壞熱,必須排除冷卻水41流動時對通 入核反應爐壓力槽1之作業性的阻礙。 因此,在燃料池冷卻淨化系統管路8的燃料池冷卻淨 化系統過濾除氯裝置11中淨化燃料池的水或來自核反應 爐井4內的冷卻水,在燃料池冷卻淨化系統熱交換器π 中所冷卻之冷卻水由燃料池循環管路17通過燃料池冷卻 淨化系統循環水注入管路19循環至燃料池5中。又,核 反應爐殘留熱去除系統管路3系統設備內的核反應爐殘留 熱去除系統之(A)系統管路23與核反應爐殘留熱去除系 統之(B或C)系統管路24等的2系統中運轉所冷卻之冷 卻水經由核反應爐殘留熱去除系統循環水注入管路31循 環至核反應爐井4中。 但,由核反應爐壓力槽1中流出的爐水中包含有放射 性包層,堆積於核反應爐井4的底部,在進行抽離核反應 爐井4的水時的核反應爐井4的底部除污作業中,會有作 業員受大量的放射線感染之可能性之問題。 本發明對上述問題提出一種核反應爐冷卻設備以及其 運轉方法,例如是在遠隔離操作核反應爐壓力槽通路之情 形下,以不降低作業性,並抑制核反應爐井之放射線以降 低放射劑量,以有效率地進行破壞熱之去除。 本發明之申請專利範圍第1項之具有在核反鹰爐井及 燃料池之間構築池閥;在此核反應爐井及燃料池之中’至 少連接有一個水源與具有過濾除氯裝置之燃料池冷卻淨化 系統管路;在前述核反應爐井的底部垂直設有核反應爐壓 8 本紙張尺度適用中國-国家標準(CNS)A<1規格(‘210 X 297公釐) (請先閱讀背面之注意事項再填寫本頁) f-----------------線 五、發明辑明(4 ) 力槽;連接於此核反應爐壓力槽之熱交換器,係具備有多 個系統之核反應爐殘留熱去除系統管路;其特徵爲:連接 於前述燃料池冷卻淨化系統管路之下游側之燃料池循環管 路之循環水注入口設置於前述核反應爐井內;以及前述核 反應爐殘留熱去除系統管路之下游側循環管路之循環水注 入口設置於前述燃料池內。 在本發明中,係利用燃料池冷卻淨化系統淨化並冷卻 循環至核反應爐井之冷卻水,及利用核反應爐殘留熱去除 系統冷卻循環至燃料池之冷卻水。如此,即可在遠隔離操 作核反應爐壓力槽通路之情形下,以不降低作業性,並抑 制核反應爐井之放射線以降低放射劑量,以有效率地進行 破壞熱之去除。 本發明之申請專利範圍第2項之具有在核反應爐井及 燃料池之間構築池閥;在此核反應爐井及燃料池之中,至 少連接有一個水源與具有過濾除氯裝置之燃料池冷卻淨化 系統管路;在前述核反應爐井的底部垂直設有核反應爐壓 力槽;連接於此核反應爐壓力槽之熱交換器,係具備有多 個系統之核反應爐殘留熱去除系統管路;其特徵爲:連接 於前述燃料池冷卻淨化系統管路之下游側之燃料池循環管 路之循環水注入口設置於前述核反應爐井內;前述核反應 爐殘留熱去除系統管路之下游側循環管路之循環水注入口 設置於前述燃料池內;以及前述燃料池冷卻淨化系統管路 之冷卻水循環至前述燃料池或前述核反應爐井,或在前述 核反應爐殘留熱去除系統管路之冷卻水循環至前述核反應 9 我--------訂---------線 {請先閱讀背面之注意事項再填寫本頁) 本紙張尺度適用中國國家標準(CNS)A.i規格(210 X 297公釐) 4 62 A7 71S6pif . doc/ 008 __^_ 五、發明說明(Q) 爐井或前述燃料池之前設置有切換操作管路。 在本發明中,係利用設置在核反應爐殘留熱去 管路上之切換操作管路之切換閥之開關操作,以調整進A 核反應爐井與燃料池之冷卻水。又,燃料池冷卻淨化系統 管路的冷卻水,可利用其他的切換操作管路循環至核 爐井。 本發明之申請專利範圍第3項之特徵爲,在前述多個 系統之核反應爐殘留熱去除系統管路之中,至少有一個系 統連接設置於前述核反應爐壓力槽內的給水噴霧器’或# 歧連接設置於前述核反應爐壓力槽內的低壓注水系統噴霧 器。 在本發明中,核反應爐壓力槽內的冷卻水之流速緩於 核反應爐殘留熱去除系統冷卻水循環至核反應爐壓力槽’ 以減少對運轉實施之作業性產生影響,如此,可並存有去 除破壞熱及提升作業性之優點。 本發明之申請專利範圍第4項之特徵爲,在前述燃料 池循環管路與燃料池冷卻淨化循環水注入管路之間,連接 有防止逆流閥與停止閥,在前述核反應爐殘留熱去除系統 中設置有熱交換器,以冷卻連接於前述燃料池冷卻淨化系 統循環水注入管路與前述核反應爐給水系統管路的冷卻水 出口側管路。 在本發明中’係利用燃料池冷卻淨化系統及核反應爐 殘留熱去除系統冷卻循環至燃料池之冷卻水,利用核反應 爐殘留熱去除系統冷卻循環至給水噴霧器之冷卻水,以在 I J ^ i I------訂---------線 (請先閲讀背面之注意事項再填寫本頁) 本紙張尺度適用中國國家標準(CNS)A‘丨規格mo X 2¾公餐) B7 462063 7l86pif.d〇c/008 五、發明說明(¾ ) 核能發電廠中,利用遠隔離操作核反應爐壓力槽通路之情 形下,以不降低作業性,並抑制核反應爐井之放射線以降 低放射劑量,以有效率地進行破壞熱之去除。 本發明之申請專利範圍第5項之具有在核反應爐井及 燃料池之間構築池閥;在前述核反應爐井的底部垂直設有 核反應爐壓力槽;連接於此核反應爐壓力槽之核反應爐殘 留熱去除系統管路;其特徵爲:前述核反應爐殘留熱去除 系統管路之下游側循環管路之循環水注入口設置於前述核 反應爐井內;以及由前述核反應爐殘留熱去除系統管路至 前述核反應爐井的上部之間分歧連接有核反應爐井取水管 路。 在本發明中,由核反應爐井之上層水流至核反應爐殘 留熱去除系統管路中,以利用此管路中之熱交換器進行冷 卻,此冷卻水再循環至核反應爐井。利用核反應爐井之乾 淨的上層水,降低被核反應爐井之放射線污染之劑量。又 核反應爐殘留熱去除系統管路的冷卻水必須循環至核反應 爐壓力槽,以在不降低作業性之情形下去除破壞熱。 本發明之申請專利範圍第6項之具有在核反應爐井及 燃料池之間構築池閥;在此核反應爐井及燃料池之中,至 少連接有一個水源與具有第一過濾除氯裝置之燃料池冷卻 淨化系統管路;在前述核反應爐井的底部垂直設有核反應 爐壓力槽;連接於此核反應爐壓力槽之熱交換器,係具備 有多個系統之核反應爐殘留熱去除系統管路;其特徵爲: 在此核反應爐殘留熱去除系統管路之冷卻水出口側配管系 <請先閱讀背面之注意事項再填寫本頁> t---------缚 本紙張尺度適用中國國家標準(CNS)/U規格(2丨〇 X 297公爱) 462063 Λ7 7186pi£-d〇c/〇°8_B7 _ 五、發明說明) 統中設置有過濾器或第二過濾除氯裝置。 本發明中,在核能發電廠中,利用遠隔離操作核反應 爐壓力槽通路之情形下,利用核反應爐殘留熱去除系統冷 卻經由過濾器或過濾除氯裝置所淨化之冷卻水以循環至核 反應爐井中,以不降低作業性,並抑制核反應爐井之放射 線以降低放射劑量,以有效率地進行破壞熱之去除。 本發明之申請專利範圍第7項之特徵爲,前述循環管 路至少連接一個設置在核反應爐井內之核反應爐井噴霧 器,前述核反應爐井噴霧器之冷卻水吹出口,各自設成朝 向前述核反應爐壓力槽之中心線之斜下方向與朝向前述中 心線之水平方向。 在本發明之中,核反應爐井噴霧器之冷卻水吹出口係 設成朝向中心線之斜下方向與朝向中心線之水平方向,以 抑制冷卻水之受放射以降低放射劑量,以進行破壞熱之去 除。 本發明之申請專利範圍第8項之特徵爲,在前述核反 應爐壓力槽內設置有低壓注水系統噴霧器’且其吹出水之 流動方向設定爲向下。低壓注水系統噴霧器之上部與內側 安裝包覆著遮蔽裝置, 在本發明之中,利用遠隔離操作核反應爐壓力槽通路 之情形下,利用核反應爐殘留熱去除系統管路冷卻循環至 低壓注水系統噴霧器之爐水之時,防止循環水直接流向核 反應爐壓力槽內的中央,以不降低作業性’並抑制放射線 以降低放射劑量,進行破壞熱之去除。 (請先閱讀背面之注意事項再填寫本頁) ^-----------------$ 本紙張尺度適用中國國家標準(CNS)A‘i規格(21CU 297公釐) Λ7 B7 718 6p i £ * doc /0 0 8 五、發明說明( 另外,在低壓注水系統噴霧器之下面,冷卻水吹出口 安裝有多個向下之噴霧器噴嘴’冷卻水由核反應爐壓力槽 與側板之間吹出’朝向核反應爐壓力槽中心方向吹出之冷 卻水,會受核反應爐之覆蓋攜入限制’而降低核反應爐井 的放射線劑量,且不妨礙遠隔離操作核反應爐壓力槽通路 之情形下之作業性,並去除破壞熱。 本發明之申請專利範圍第9項之特徵爲’在前述燃料 池內之多數冷卻水吹出孔上設置有多個棚段狀擴散器。在 此發明之中,在燃料池內設置有上下多個棚段狀擴散器, 配管口徑擴大,可使大量的冷卻水循環至燃料池中’以在 燃料池內進行有效地佈局。 本發明之申請專利範圍第10項之特徵爲’在前述核 反應爐內設置有2系統的給水噴霧器,以連接第一給水管 路與第二給水管路,在此給水管路與核反應爐冷卻材料浄 化系統管路之間連接有第一防止逆流閥與第二防止逆流 閥,此核反應爐冷卻材料淨化系統管路,係前述第一袷水 管路與前述第一防止逆流閥之間連接有前述核反應爐殘® 熱去除系統管路,且前述第一防止逆流閥係爲具強制_璣 功能之防止逆流閥。 在本發明之中,具強制開機功能之防止逆流閥係流向 冷卻材料之相反方向。因此,核反應爐冷卻材料淨化系統 管路安裝電動閥或來自核反應爐殘留熱去除系統管路,迎 經由給水系統停止閥之核反應爐給水系統的第一給水嘴_ 管路或第二給水噴霧管路擇一之冷卻水循環供應。可抑制 — — — — — — — — — — — — _ 11 ί 11 J-*-'§T,lt — — — — — —1 , (請先閱讀背面之注意事項再填寫本頁} 本紙張尺度適用中國國家標準(CNS)A.l規格(2K! X 297公釐) 4 620 6 3 7186pif . doc/00Θ Α7 Β7" Zai ^ All meet with the bombers ^ as a fee ^^-^, · " ^ 620 63 A7 7 186pif -doc / 00 8 B7 V. Description of the invention (I) μμμμ. The present invention is about nuclear power generation In the case of the passage in the pressure tank of the nuclear reactor in the plant, the nuclear reactor cooling equipment and the operation method thereof do not impair the workability, suppress the radiation from the nuclear reactor well, reduce the amount of radiation, and remove the possibility of thermal decay. BACKGROUND OF THE INVENTION Please refer to FIG. 16 to describe a nuclear reactor cooling facility in an improved boiling water type nuclear power plant. Fig. 16 shows a simplified pipe system of a conventional nuclear reactor cooling equipment. In Fig. 16, the symbol 1 is the pressure tank of the nuclear reaction furnace with the upper cover taken out, and the side plate top cover on the furnace core 2 indicates the state of removing the gas-liquid separator and the steam dryer. The reference numeral 3 indicates a simplified internal pump. The thick line in Fig. 16 indicates the water flow state of the boiler water or pool water, and the thin line indicates the non-water flow state. In FIG. 16, the outer side of the upper opening portion of the nuclear reactor pressure tank 1 is constructed in a nuclear reactor building (not shown), and a watertight connection material (not shown) is installed at the bottom of the nuclear reactor shaft 4. ). The bottom of the pressure tank 1 of the nuclear reactor is supported by a base (not shown). The nuclear reactor 4 is distinguished from the fuel pool by a pool valve 6. In the fuel pool 5 and the nuclear reactor shaft 4, a gap pressure regulating tank 7 adjacent to a plurality of base devices is adjacent. The gap pressure regulating tank 7 is an empty tank into which the upper liquid of the overflow water in the fuel pool 5 and the nuclear reactor shaft 4 flows. The bottom of the tank is connected to the fuel tank cooling purification system (FPC) pipeline 8 for the bottom. Fuel tank cooling and purification system pipe 8 is connected in series with an inlet stop 4 ----- ^ -------- Order · -------- line (please read the unintentional on the back first) Please fill in this page again) This paper size is applicable to China (CNS) A: I specificationI0 X 297 mm) 620 6 3 Λ7 7186pif.doc / 008 ㈤ V. Description of the invention ()) Valve 9, fuel tank cooling purification system pump 10. Fuel tank cooling and purification system filtering and dechlorination device U, outlet stop valve 12 and fuel pool cooling and purification system heat exchanger 13; fuel pool cooling and purification system filtering and dechlorination device 11 upstream and downstream outlet stop valves 12 The outlet side is connected to a fuel tank cooling and purifying system side pipe line 15 having a side pipe valve 14. The fuel pool cooling and purifying system pump 10, the fuel pool cooling and purifying system filter 11 and the fuel pool cooling and purifying system heat exchanger 13 are each provided with two identical devices in parallel. A fuel cell cooling and purifying system filtering and dechlorinating device 11 and an outlet stop valve 12 are connected to a suppression pool purifying system (abbreviated as SPCU) line 16 at the branch. The downstream side of the heat exchanger 13 of the fuel pool cooling and purifying system is connected to a fuel pool circulation pipe 17, and the fuel pool circulation pipe 17 is connected to the fuel pool cooling and purification system circulating water injection pipe 19 via a backflow prevention valve 18. A circulating water injection pipe 19 is provided in the fuel pool 5, and a lower end of the circulating water injection pipe 19 is provided with a circulating water injection port. A suppression pool purification system pipeline 16 is provided at the nuclear reactor shaft 4 and is connected to the suppression pool purification system pipeline 16 located at the outlet side of the filtering and dechlorination device Π of the fuel pool cooling purification system. Between the outlet side of the inlet stop valve 9 of the fuel pool cooling and purifying system pipe 8 and the nuclear reactor shaft 4, a nuclear reactor shaft connecting pipe 22 containing a fuel pool cooling and purifying system including a stop valve 21 is provided. The inlet side of the inlet stop valve 9 of the fuel pool cooling and purifying system pipeline 8 uses (A) system pipelines 23 of the nuclear reactor residual heat removal system which are connected to the nuclear reactor residual heat removal system (RHR) pipelines respectively. Residual Heat Removal System of Nuclear Reactor 5 ί I ^ --- J I --- # ·! ------ ^, (Please read the precautions on the back before filling this page) This paper is adequate for China Standard < CNS) A4 Specification < 210 X 297 mm) 462063 A7 7 1 8 6pi f. Doc / 〇〇8 g- V. Description of the invention | [,] System (B or c) system pipe 24 of The fuel cell cooling and purifying system-nuclear reactor residual heat removal system connection pipe 28 of the stop valves 27a to 27c is connected to the nuclear reactor pressure tank 1. There are 3 systems of 1st to 3rd grade in the residual heat removal system pipeline of the nuclear reactor. In the description of the relationship, it is divided into the (A) system pipeline 23 of the residual heat removal system of the nuclear reactor and the residual heat of the nuclear reactor. Remove system (B or C) system line 24. The (A) system piping 23 of the nuclear reactor residual heat removal system and the (B or C) system piping 24 of the nuclear reactor residual heat removal system are each connected in series with a nuclear reactor residual heat removal system pump 25 and a nuclear reaction. The furnace residual heat removal system heat exchanger 26 is connected on its downstream side to the fuel pool circulation pipeline 17 by a nuclear reactor furnace residual heat removal system-fuel pool cooling and purification system connection line 29. The nuclear reactor furnace residual heat removal system circulating water injection pipeline divided by the nuclear reactor furnace residual heat removal system-fuel pool cooling and purification system connection line 29 is provided with a nuclear reactor furnace residual heat removal system circulating water near the bottom inside the nuclear reactor furnace 4 Inject □ 30. In Fig. 16, reference numerals 32, 33, 34a, and 34b indicate stop valves, respectively, and reference numeral 35 indicates a nuclear reactor feed water system (FDW). The nuclear reactor furnace water supply system 35 is provided with a first feed water spraying pipeline 46 and a second feed water spraying pipeline 47. Here, the feed water spraying pipelines 46 and 47 are respectively connected to two feed water sprayers arranged in the pressure tank of the nuclear reactor. 37, 37. The (A) system pipe 23 of the residual heat removal system of the nuclear reactor is branched to the branch pipe 38, and is connected to the first water supply spray pipe 46 through a stop valve 39. In addition, the (B or C) system tube of the residual heat removal system of the nuclear reactor 6 This paper size applies to the Chinese National Standard (CNS) Al specification (210x297) (please read the precautions on the back before filling this page) '' Binding- -------- Line 462063 A7 7lS6pif.doc / 008 β- V. Description of the invention (Ψ) The circuit 24 is connected to the spray line of the low-pressure water injection system (referred to as LPFL), and the spray line 45 of the low-pressure water injection system is connected to A plurality of low-pressure water injection system sprayers 36 arranged in the pressure tank 1 of the nuclear reactor are connected. Here, the 1st system of the nuclear reactor residual heat removal system (the (A) system of the nuclear reactor residual heat removal system) 23 is connected to the water supply sprayer 37 of the nuclear reactor furnace water supply system 35 so that the water supply sprayer 37 is circulated to In the nuclear reactor pressure tank 1, the other two systems (the (B or C) system of the nuclear reactor residual heat removal system) 24 are circulated to the nuclear reactor pressure tank 1 using a low-pressure water injection system sprayer 36. There are three water supply sprayers 37 in the first system, and six in total in the two systems. There is one low pressure water injection system sprayer 36 in the first system, and two in total. In Fig. 16, reference numeral 40 indicates the height of the working ground, reference numeral 41 indicates the cooling water, reference numeral 42 indicates the liquid level of the cooling water 41, and reference numeral 43 indicates a stop valve provided on the circulating water injection pipe 31 of the residual heat removal system of the nuclear reactor. Reference numeral 44 denotes a stop valve provided on the low-pressure water injection system pipe 45 and connected to the low-pressure water injection system sprayer 36 at the same time. The invention describes a boiling water type nuclear reactor equipped with a core assembly 2 loaded with a fuel assembly in a nuclear power plant, which is introduced into the pressure tank 1 of the nuclear reactor for exchange of control rods. Basically, the operation starts at a working floor height of 40. The operation is transformed into a long film operation. However, the influence of the cooling water flow in the nuclear reactor 4 or the fuel pool 5 must be eliminated. In this case, in the current improved boiling water type nuclear reactor, the fuel assembly 7 existing in the pressure tank 1 or the fuel pool 5 of the nuclear reactor is removed. ----- Line (Jing first read the notes on the back before filling this page) This paper size is applicable to Chinese National Standard (CNS) Al specification (210 X 297 mm) 4.620 6 3 7186pif.doc / 008 Λ7 Ei7 V. DISCLOSURE OF THE INVENTION The initial destruction heat of the fuel in the (?) Must be prevented from hindering the workability of the flow into the nuclear reactor pressure tank 1 when the cooling water 41 flows. Therefore, the fuel pool cooling and purifying system in the fuel pool cooling and purifying system pipeline 8 filters the water purifying the fuel pool in the chlorine removal device 11 or the cooling water from the nuclear reactor well 4 in the fuel pool cooling and purifying system heat exchanger π. The cooled cooling water is circulated to the fuel pool 5 through the fuel pool circulation pipeline 17 through the fuel pool cooling and purification system circulating water injection pipeline 19. In addition, there are 2 systems of the nuclear reactor furnace residual heat removal system pipeline 3 (A) system pipeline 23 of the nuclear reactor furnace residual heat removal system and (B or C) system pipeline 24 of the nuclear reactor furnace residual heat removal system. The cooling water cooled in the middle operation is circulated to the nuclear reactor shaft 4 through the circulating water injection pipe 31 of the residual heat removal system of the nuclear reactor. However, the boiler water flowing out of the nuclear reactor furnace pressure tank 1 contains a radioactive cladding, which is deposited on the bottom of the nuclear reactor furnace 4 and is used for decontamination of the bottom of the nuclear reactor furnace 4 when the water is removed from the nuclear reactor furnace 4 There is a problem of the possibility that the operator will be infected with a large amount of radiation. The present invention proposes a nuclear reactor cooling equipment and a method for operating the same. For example, in the case of remotely operating a nuclear reactor pressure tank path, the workability is not reduced, and the radiation in the nuclear reactor well is suppressed to reduce the radiation dose. Efficient removal of destruction heat. The invention has the scope of the patent application No. 1 has the construction of a pool valve between the nuclear anti-eagle furnace shaft and the fuel pool; in this nuclear reaction furnace shaft and the fuel pool 'at least one water source is connected to the cooling of the fuel pool with a filter chlorine removal device Purification system piping; a nuclear reactor pressure is set vertically at the bottom of the aforementioned nuclear reactor shaft. 8 This paper size is applicable to China-National Standard (CNS) A < 1 specification ('210 X 297 mm) (Please read the precautions on the back first) (Fill in this page again) f ----------------- line five, inventions (4) force tank; the heat exchanger connected to the pressure tank of the nuclear reactor is equipped with Residual heat removal system piping of nuclear reactors of multiple systems; characterized in that: a circulating water injection port of a fuel pool circulation pipeline connected to the downstream side of the aforementioned fuel pool cooling and purification system pipeline is provided in the aforementioned nuclear reactor furnace well; and The circulating water injection port of the downstream side circulation pipe of the pipe of the residual heat removal system of the nuclear reactor is disposed in the fuel pool. In the present invention, the cooling water circulating to the nuclear reactor well is purified and cooled by the fuel pool cooling and purifying system, and the cooling water circulating to the fuel pool is cooled by the residual heat removal system of the nuclear reactor. In this way, in the case of remotely operating the pressure channel of the nuclear reactor, the workability is not reduced, and the radiation of the nuclear reactor well is suppressed to reduce the radiation dose, so that the destruction heat can be efficiently removed. The second scope of the patent application of the present invention has a valve for constructing a pool between a nuclear reactor well and a fuel pool; in the nuclear reactor well and the fuel pool, at least one water source is connected to a cooling and purifying system of a fuel pool having a filter and chlorine removal device Pipeline; a nuclear reactor pressure tank is vertically arranged at the bottom of the aforementioned nuclear reactor furnace shaft; a heat exchanger connected to this nuclear reactor furnace pressure tank is a nuclear reactor furnace residual heat removal system pipeline with multiple systems; its characteristics are: The circulating water injection port of the fuel pool circulation pipeline connected to the downstream side of the fuel pool cooling and purification system pipeline is provided in the nuclear reactor well; the circulating water of the downstream circulation pipeline of the nuclear heat furnace residual heat removal system pipeline The injection inlet is set in the aforementioned fuel pool; and the cooling water of the fuel pool cooling and purification system pipeline is circulated to the aforementioned fuel pool or the nuclear reactor well, or the cooling water of the residual heat removal system pipeline of the nuclear reactor is recycled to the aforementioned nuclear reaction 9 I -------- Order --------- Line {Please read the precautions on the back before filling this page) This paper size With China National Standard (CNS) A.i size (210 X 297 mm) 4 62 A7 71S6pif. Doc / 008 __ ^ _ V. description of the invention (Q) is provided with a switching operation of the well or the conduit prior to the furnace fuel pool. In the present invention, the switching operation of the switching valve of the switching operation pipeline provided on the residual heat removal pipeline of the nuclear reactor is used to adjust the cooling water entering the nuclear reactor well and the fuel pool. In addition, the cooling water of the fuel pool cooling and purification system pipeline can be circulated to the nuclear furnace well by other switching operation pipelines. The third feature of the scope of patent application of the present invention is that, among the pipes of the residual heat removal system of the nuclear reactor in the foregoing multiple systems, at least one system is connected to the water supply sprayer or the manifold in the pressure tank of the nuclear reactor. Connected to the low-pressure water injection system sprayer set in the pressure tank of the nuclear reactor. In the present invention, the flow rate of the cooling water in the pressure tank of the nuclear reactor is slower than that of the residual heat removal system of the nuclear reactor. The cooling water is circulated to the pressure tank of the nuclear reactor to reduce the impact on the operability of the operation. And the advantages of improving workability. The fourth feature of the scope of the patent application of the present invention is that a reverse flow prevention valve and a stop valve are connected between the fuel pool circulation pipeline and the fuel pool cooling and purification circulating water injection pipeline, and the residual heat removal system in the nuclear reactor is described above. A heat exchanger is provided to cool the cooling water outlet side pipeline connected to the circulating water injection pipeline of the cooling and purification system of the fuel pool and the pipeline of the water supply system of the nuclear reactor. In the present invention, the cooling water circulating to the fuel pool is cooled by the fuel pool cooling and purification system and the residual heat removal system of the nuclear reactor, and the cooling water is circulated to the cooling water of the water supply sprayer by the residual heat removal system of the nuclear reactor, so that ----- Order --------- Line (Please read the precautions on the back before filling this page) This paper size applies to China National Standard (CNS) A '丨 size mo X 2¾ Meal) B7 462063 7l86pif.d〇c / 008 V. Description of the Invention (¾) In the case of nuclear power plants, the remote reactor operation of the pressure tank channel of the nuclear reactor, in order not to reduce workability, and to suppress the radiation of the nuclear reactor well to reduce the radiation dose To efficiently remove the heat of destruction. The invention has the scope of application patent No. 5 having a valve for constructing a pool between a nuclear reactor shaft and a fuel pool; a nuclear reactor pressure tank is vertically arranged at the bottom of the aforementioned nuclear reactor shaft; a nuclear reactor furnace residual heat connected to the nuclear reactor furnace pressure tank The removal system pipeline is characterized in that: a circulating water injection port of a downstream side circulation pipeline of the nuclear reactor furnace residual heat removal system pipeline is provided in the nuclear reactor furnace well; and the nuclear reactor furnace residual heat removal system pipeline is connected to the foregoing The upper part of the nuclear reactor well is connected to the water intake pipeline of the nuclear reactor well. In the present invention, the water from the upper layer of the nuclear reactor shaft is flowed into the pipe of the residual heat removal system of the nuclear reactor to be cooled by the heat exchanger in the pipeline, and the cooling water is recycled to the nuclear reactor shaft. Use the clean upper water of the nuclear reactor shaft to reduce the dose of radiation contamination from the nuclear reactor shaft. In addition, the cooling water of the residual heat removal system piping of the nuclear reactor must be circulated to the pressure tank of the nuclear reactor, so as to remove the destruction heat without reducing the workability. The invention has the scope of application patent No. 6 having a valve for constructing a pool between the nuclear reactor well and the fuel pool; in the nuclear reactor well and the fuel pool, at least one water source is connected to the cooling of the fuel pool having the first filtering chlorine removal device Purification system pipeline; a nuclear reactor pressure tank is vertically arranged at the bottom of the aforementioned nuclear reactor furnace shaft; a heat exchanger connected to this nuclear reactor furnace pressure tank is a nuclear reactor furnace residual heat removal system pipeline with multiple systems; its characteristics For: The piping of the cooling water outlet side of the piping of the residual heat removal system of this nuclear reactor < Please read the precautions on the back before filling this page > National Standard (CNS) / U specification (2 丨 〇X 297 public love) 462063 Λ7 7186pi £ -d〇c / 〇 ° 8_B7 _ 5. Description of the invention) A filter or a second filtering chlorine removal device is provided in the system. In the present invention, in a nuclear power plant, in the case of remotely operating a pressure reactor channel of a nuclear reactor, the residual heat removal system of the nuclear reactor is used to cool the cooling water purified through a filter or a filter chlorine removal device to circulate to the nuclear reactor well. In order not to reduce the workability, and to suppress the radiation of the nuclear reactor furnace to reduce the radiation dose, in order to efficiently remove the destruction of heat. The seventh feature of the scope of patent application of the present invention is that the circulation pipeline is connected to at least one nuclear reactor furnace sprayer arranged in the nuclear reactor furnace well, and the cooling water blow-out port of the nuclear reactor furnace sprayer is respectively set to face the nuclear reactor The oblique downward direction of the center line of the pressure groove and the horizontal direction toward the aforementioned center line. In the present invention, the cooling water blow-out port of the well sprayer of the nuclear reactor is set to the oblique downward direction toward the center line and the horizontal direction toward the center line, so as to suppress the radiation of the cooling water and reduce the radiation dose, so as to destroy the heat. Remove. Item 8 of the scope of patent application of the present invention is characterized in that a low-pressure water injection system sprayer 'is provided in the pressure tank of the nuclear reactor and the flow direction of the blown water is set downward. The upper part and the inner side of the low-pressure water injection system sprayer are covered with a shielding device. In the present invention, in the case of using a remote isolation to operate the pressure channel of the nuclear reactor, the residual heat removal system pipe of the nuclear reactor is used to cool the circulation to the low-pressure water injection system sprayer. When the furnace water is used, the circulating water is prevented from flowing directly to the center of the pressure tank of the nuclear reactor, so that the workability is not reduced, the radiation is suppressed to reduce the radiation dose, and the destruction heat is removed. (Please read the precautions on the back before filling this page) ^ ----------------- $ This paper size is applicable to China National Standard (CNS) A'i specifications (21CU 297) (B) Λ7 B7 718 6p i £ * doc / 0 0 8 V. Description of the invention (In addition, under the low-pressure water injection system sprayer, the cooling water blowing outlet is equipped with a plurality of downward sprayer nozzles. The cooling water is supplied from the pressure tank of the nuclear reactor. The cooling water blown out towards the center of the pressure tank of the nuclear reactor is blown between the side plate and the cover of the nuclear reactor, and the radiation dose of the nuclear reactor well is reduced, and it does not prevent the remote isolation operation of the channel of the reactor pressure tank. The workability of the invention is reduced, and the destruction heat is removed. The ninth feature of the scope of patent application of the present invention is that a plurality of shed-like diffusers are provided on most of the cooling water blow-out holes in the aforementioned fuel pool. In this invention In the fuel pool, a plurality of upper and lower shed-like diffusers are provided, and the diameter of the piping is enlarged, so that a large amount of cooling water can be circulated to the fuel pool to effectively lay out in the fuel pool. The scope of patent application for the present invention is item 10 Of It is characterized in that a two-system water supply sprayer is provided in the aforementioned nuclear reaction furnace to connect the first water supply pipeline and the second water supply pipeline, and a first water supply pipeline is connected between the water supply pipeline and the cooling material purification system pipeline of the nuclear reaction furnace. The anti-backflow valve and the second anti-backflow valve, the cooling material purification system piping of the nuclear reactor, are connected with the nuclear reactor furnace residual heat removal system piping between the first sluicing water pipe and the first anti-reverse valve, and The aforementioned first backflow prevention valve is a backflow prevention valve with a forced 玑 function. In the present invention, the backflow prevention valve system with a forced start function flows in the opposite direction to the cooling material. Therefore, the nuclear reaction furnace cooling material purification system pipeline Install electric valve or the pipe from the residual heat removal system of the nuclear reactor, and circulate the cooling water supply of the first water nozzle_pipe or the second water spray pipe of the nuclear reactor furnace water supply system via the water supply system stop valve. — — — — — — — — — — — _ 11 ί 11 J-*-'§T, lt — — — — — — 1, (Please read the note on the back first } This page item and then fill in the paper scale applicable Chinese National Standard (CNS) A.l size (2K! X 297 mm) 4 620 6 3 7186pif. Doc / 00Θ Α7 Β7

五、發明說明(丨I ) 燃料交換對核反應爐壓力槽內之作業性之影響’並去除破 壞熱。 本發明之申請專利範圍第11項之具有在核反應爐井 及燃料池之間構築池閥;在此核反應爐井及燃料池之中’ 至少連接有一個水源與具有過濾除氯裝置之燃料池冷卻淨 化系統管路;在前述核反應爐井的底部垂直設有核反應爐 壓力槽:連接於此核反應爐壓力槽之熱交換器’係具備有 核反應爐殘留熱去除系統管路;其特徵爲:由前述核反應 爐殘留熱去除系統管路分岐連接再生熱交換器’及設有具 過濾除氯裝置之核反應爐冷卻材料淨化系統管路,此核反 應爐冷卻材料淨化系統管路的過濾除氯裝置之出口側連接 有連接於該核反應爐給水系統管路之核反應爐冷卻材料淨 化系統循環管路;以及在前述核反應爐冷卻材料淨化系統 循環管路上設有具有側管熱交換器之核反應爐冷卻材料淨 化系統側管管路。 在本發明之中’於核反應爐冷卻材料淨化系統側管管 路之側管上設於核反應爐冷卻材料淨化再生熱交換器,利 用其運轉可提升其去除破壞熱之效率。 本發明之申請專利範圍第12項,係具備有在核反應 爐井及燃料池之間構築池閥;在此核反應爐井及燃料池之 中’至少連接有一個水源、過濾除氯裝置及具有熱交換器 之燃料池冷卻淨化系統管路;在前述核反應爐井的底部垂 直設有核反應爐壓力槽;此核反應爐壓力槽經由停止閥連 接具備依序連接有核反應爐殘留熱去除系統管路之熱交換 本纸張尺度適用中國國家標準(CNS)A4規格(21CU 297公楚> ¾--------tr---------線 (請先閱讀背面之注意事項再填寫本頁) 涇齊郎替逢討查笱員二淖費合阼.:i,fv,f' 4 6 2 0 6 3 A7 7136pif.doc/008 g- 五、發明說明(p) 器的核反應爐冷卻設備之運轉方法,其特徵爲前述燃料池 冷卻淨化系統管路的過濾除氯裝置中設有具側管閥之側管 管路;以及此側管管路之前述側管閥爲開啓狀態時,流向 前述燃料池冷卻淨化系統管路之熱交換器的流量會增加。 在本發明之中,燃料池冷卻淨化系統之過濾除氯裝置 的側管閥開啓時會增大燃料池冷卻淨化系統之系統流量, 且在燃料池冷卻淨化系統之熱交換器的流量增大時,也會 提高燃料池冷卻淨化系統之除熱效率。 本發明之申請專利範圍第13項,係具備有在核反應 爐井及燃料池之間構築池閥;在此核反應爐井及燃料池之 中,至少連接有一個水源與具有過濾除氯裝置之燃料池冷 卻淨化系統管路;在前述核反應爐井的底部垂直設有核反 應爐壓力槽;連接於此核反應爐壓力槽之具備有多個系統 之核反應爐殘留熱去除系統管路之熱交換器:連接前述核 反應爐殘留熱去除系統管路與前述燃料池冷卻淨化系統管 路之核反應爐殘留熱去除系統-燃料池冷卻淨化系統連接 管路的核反應爐冷卻設備之運轉方法,其特徵爲前述多個 系統之核反應爐殘留熱去除系統係具有第一系統至第三系 統之三系統、第一系統係利用此系統之熱交換器冷卻前述 核反應爐給水系統或循環至前述燃料池的冷卻水、第二系 統係利用此系統之熱交換器冷卻循環至前述燃料池的冷卻 水、第三系統也是利用此系統之熱交換器冷卻循環至前述 燃料池的冷卻水;前述燃料池冷卻淨化系統管路係由前述 燃料池水中取水,淨化之後,經由抑制池淨化系統循環至 I -----装-----1--訂--------線 (請先閱讀背面之注意事項再填寫本頁) 本紙張尺度適用中國國家標準(CNS)A4規格(210 x 297公釐) 4 62063V. Description of the Invention (丨 I) Effect of fuel exchange on operability in the pressure tank of a nuclear reactor 'and removal of heat of destruction. The invention has the scope of the patent application No. 11 having a pool valve constructed between the nuclear reactor well and the fuel pool; in this nuclear reactor well and the fuel pool, at least one water source is connected to the cooling and purification system of the fuel pool with a filter and chlorine removal device Pipeline; a nuclear reactor pressure tank is vertically arranged at the bottom of the nuclear reactor furnace shaft: the heat exchanger connected to the nuclear reactor furnace pressure tank is equipped with a nuclear reactor residual heat removal system pipeline; it is characterized by: The residual heat removal system pipeline is divided into a regenerative heat exchanger 'and a nuclear reactor cooling material purification system pipeline provided with a filter and chlorine removal device. The nuclear reactor furnace cooling material purification system pipeline is connected to the outlet side of the filter and chlorine removal device. The nuclear reaction furnace cooling material purification system circulation pipeline connected to the nuclear reaction furnace water supply system pipeline; and the nuclear reaction furnace cooling material purification system circulation pipeline with a side tube heat exchanger provided with the side reaction tube road. In the present invention, the side pipe of the cooling pipe purification system of the nuclear reaction furnace is provided on the side pipe of the nuclear reaction furnace cooling material purification and regeneration heat exchanger, and its operation can improve the efficiency of removing the destruction heat. Item 12 of the scope of patent application of the present invention is provided with a pool valve constructed between the nuclear reactor shaft and the fuel pool; in this nuclear reactor shaft and the fuel pool, at least one water source, a filtering and dechlorinating device and a heat exchanger are connected. The fuel tank cooling and purification system pipeline; a nuclear reactor pressure tank is vertically arranged at the bottom of the aforementioned nuclear reactor furnace shaft; this nuclear reactor pressure tank is connected via a stop valve with a heat exchange book that sequentially connects the nuclear reactor furnace residual heat removal system pipeline Paper size applies to China National Standard (CNS) A4 (21CU 297 cm) ¾ -------- tr --------- line (Please read the precautions on the back before filling in this P.) Qi Qilang meets with the investigator and discusses the cost of the two members.:i,fv,f '4 6 2 0 6 3 A7 7136pif.doc / 008 g- V. Description of the invention (p) Nuclear reactor cooling The operation method of the device is characterized in that a side pipe valve with a side pipe valve is provided in the filtering and dechlorination device of the fuel pool cooling and purification system pipe; and when the side pipe valve of the side pipe pipe is open, Flow to the heat exchanger of the aforementioned fuel pool cooling and purification system In the present invention, when the side pipe valve of the filtering and dechlorinating device of the fuel pool cooling and purifying system is opened, the system flow of the fuel pool cooling and purifying system is increased, and the flow rate of the heat exchanger of the fuel pool cooling and purifying system is increased. When it is large, it will also improve the heat removal efficiency of the fuel pool cooling and purification system. The 13th scope of the patent application of the present invention is equipped with a pool valve between the nuclear reactor well and the fuel pool; in this nuclear reactor well and the fuel pool, At least one water source is connected to the pipeline of the fuel pool cooling and purifying system with a filtering and dechlorinating device; a nuclear reactor pressure tank is vertically arranged at the bottom of the aforementioned nuclear reactor shaft; a nuclear reaction equipped with multiple systems is connected to the nuclear reactor pressure tank Heat exchanger of the furnace residual heat removal system pipeline: a nuclear reactor that connects the residual heat removal system pipeline of the nuclear reactor and the fuel pool cooling purification system pipeline to the nuclear reactor residual heat removal system-fuel pool cooling purification system connection pipeline Method for operating cooling equipment, characterized in that the residual heat removal system of the nuclear reactor in the foregoing multiple systems The third system includes the first system to the third system, the first system uses the heat exchanger of this system to cool the water supply system of the nuclear reactor or the cooling water circulating to the fuel pool, and the second system uses the heat exchange of this system The cooling water of the fuel tank is circulated to the aforementioned fuel pool, and the third system also uses the heat exchanger of this system to cool the cooling water circulated to the aforementioned fuel pool; the pipeline of the fuel pool cooling and purification system takes water from the fuel pool water, and after purification, , Through the suppression tank purification system to cycle to I ----- install ----- 1--order -------- line (please read the precautions on the back before filling this page) This paper size applies China National Standard (CNS) A4 (210 x 297 mm) 4 62063

Ki 7186pif_doc/008 37 __ 五、發明說明(〇 ) 前述核反應爐井或機器預置池。 在本發明之中,利用核反應爐殘留熱去除系統之3系 統的冷卻運轉,可完全具有規格之運轉50%程度之系統流 量的除熱能力。因此可在循環至燃料池及給水噴霧器之過 程中降低受核反應爐井感染之放射線劑量。 又,利用燃料池冷卻淨化系統之淨化運轉時,可在其 過濾除氯裝置之出口與核反應爐井之間增設抑制池淨化系 統或循環至增設於核反應爐井附近之機器預置池。 本發明之申請專利範圍第14項之特徵爲,係具備有 在核反應爐井及燃料池之間構築池閥;在此核反應爐井及 燃料池之中,至少連接有一個水源與具有過濾除氯裝置之 燃料池冷卻淨化系統管路;在前述核反應爐井的底部垂直 設有核反應爐壓力槽;連接於此核反應爐壓力槽之具有核 反應爐殘留熱去除系統管路之熱交換器的核反應爐冷卻設 備之運轉方法,其特徵爲前述核反應爐殘留熱去除系統係 具有第一系統至第三系統之三系統、在前述第一系統至前 述第三系統中,係各自設有至少2個串連連接運轉的熱交 換器。 在本發明之中,多個的核反應爐殘留熱去除系統之熱 交換器利用串連連接運轉,以提高前述核反應爐殘留熱去 除系統管路之除熱效率,又,可自低壓注水系統或給水噴 霧器運轉循環至核反應爐壓力槽中。 爲讓本發明之上述和其他目的、特徵、和優點能更明 顯易懂,下文特舉一較佳實施例,並配合所附圖式,作詳 16 本紙張尺度適用中國國家標準(CNS)A4規格(210 X 297公f ) ^--------tr---------^ (諳先閱讀背面之注意事項再填寫本頁》 6 20 6 3 7186pif.doc/008 五、發明說明(丨11) 細說明如下: 圖式之.簡單說明 第1圖所示爲本發明之第一較佳實施例之核反應爐冷 卻設備的系統圖。 第2圖所示爲本發明之第二較佳實施例之核反應爐冷 卻設備的系統圖。 第3圖所示爲本發明之第二較佳實施例之其他形式之 核反應爐冷卻設備的系統圖。 第4圖所示爲本發明之第三較佳實施例之核反應爐冷 卻設備的系統圖。 第5圖所示爲本發明之第四較佳實施例之核反應爐冷 卻設備的系統圖。 第6圖所示爲本發明之第五較佳實施例之核反應爐冷 卻設備的局部截面圖。 第7圖所示爲本發明之第六較佳實施例之核反應爐冷 卻設備的槪略截面圖。 第8圖所示爲本發明之第七較佳實施例之核反應爐冷 卻設備的局部截面圖。 第9圖所示爲本發明之第八較佳實施例之核反應爐冷 卻設備的槪略截面圖。 第10a圖所示爲本發明之第九較佳實施例之核反應爐 冷卻設備的槪略截面圖。 第10b圖所示爲在第10a圖中之LPFL噴霧器的放大 斜視圖。 ^--------t--------- <請先間讀背面之注意事項再填寫本頁) 本纸張尺度適用中國國家標準(CN.S)A4規格(210 X 297公堃) 462063 ^ 7186pif.doc/008 五、發明說明((<) 第lla圖所示爲本發明之第十較佳實施例之核反應爐 冷卻設備之局部側面的縱截面圖。 第lib圖所示爲第lla圖的俯視圖。 第12圖所示爲本發明之第十一較佳實施例之核反應 爐冷卻設備的系統圖。 第13圖所示爲本發明之第十二較佳實施例之核反應 爐冷卻設備及說明本發明之第一較佳實施例之核反應爐冷 卻設備之運轉方法的系統圖。 第14圖所示爲本發明之第二較佳實施例之核反應爐 冷卻設備之運轉方法的系統圖。 第15圖所示爲本發明之第三較佳實施例之核反應爐 冷卻設備之運轉方法的系統圖。 第16圖所示爲習知之核反應爐冷卻設備的系統圖。 圖式之標記說明: 1 :核反應爐壓力槽 2 :爐心 3 :內泵 4:核反應爐井 5 :燃料池 6 :池閥 7:間隙調壓槽 8:燃料池冷卻淨化系統管路 9:進口停止閥 10 :燃料池冷卻淨化系統泵 ---------------I I (請先閱讀背面之注意事項再填寫本頁) 本紙張尺度適用中固國家標準(CNS)A.l規格(210 χ 297公釐〉 4 6 2 0 6 3Ki 7186pif_doc / 008 37 __ 5. Description of the invention (〇) The aforementioned nuclear reactor well or machine preset pool. In the present invention, the cooling operation of the 3 system using the residual heat removal system of the nuclear reactor can completely remove the heat of the system with a flow rate of about 50% of the system. It is therefore possible to reduce the radiation dose from infections in the nuclear reactor wells during the cycle to the fuel pool and feedwater sprayer. In addition, during the purification operation using the fuel pool cooling purification system, a suppression pool purification system can be added between the outlet of the filtering chlorine removal device and the nuclear reactor well or it can be circulated to a machine preset pool added near the nuclear reactor well. The feature of item 14 of the scope of patent application of the present invention is that it has a valve for constructing a pool between the nuclear reactor well and the fuel pool; in this nuclear reactor well and the fuel pool, at least one water source is connected with a filtering and dechlorinating device. Fuel tank cooling and purification system piping; a nuclear reactor pressure tank is vertically arranged at the bottom of the nuclear reactor well; a nuclear reactor cooling equipment of a heat exchanger having a nuclear reactor residual heat removal system pipeline connected to the nuclear reactor pressure tank The operating method is characterized in that the residual heat removal system of the nuclear reactor has three systems of a first system to a third system, and the first system to the third system are each provided with at least two serially connected operation Heat exchanger. In the present invention, the heat exchangers of the residual heat removal system of a plurality of nuclear reactors are operated in series connection to improve the heat removal efficiency of the pipelines of the residual heat removal system of the nuclear reactor, and the low-pressure water injection system or the water sprayer can be used. The operation is circulated to the pressure tank of the nuclear reactor. In order to make the above and other objects, features, and advantages of the present invention more comprehensible, a preferred embodiment is given below, in conjunction with the accompanying drawings, for details. 16 This paper size applies to Chinese National Standard (CNS) A4. Specifications (210 X 297 male f) ^ -------- tr --------- ^ (谙 Please read the notes on the back before filling in this page "6 20 6 3 7186pif.doc / 008 V. Description of the invention (11) A detailed description is as follows: Figure 1. Brief description The first figure shows the system diagram of the nuclear reactor cooling equipment of the first preferred embodiment of the present invention. The second figure shows the present invention The second preferred embodiment of the nuclear reactor cooling equipment system diagram. Figure 3 shows the second preferred embodiment of the present invention in another form of nuclear reactor cooling equipment system diagram. Figure 4 shows this System diagram of the nuclear reactor cooling equipment of the third preferred embodiment of the invention. Figure 5 shows the system diagram of the nuclear reactor cooling equipment of the fourth preferred embodiment of the invention. Figure 6 shows the system of the invention. The fifth preferred embodiment is a partial cross-sectional view of the cooling equipment of a nuclear reactor. A schematic cross-sectional view of the nuclear reactor cooling equipment of the sixth preferred embodiment. Figure 8 shows a partial cross-sectional view of the nuclear reactor cooling equipment of the seventh preferred embodiment of the present invention. Figure 9 shows the present invention. A schematic cross-sectional view of the cooling equipment of a nuclear reactor in an eighth preferred embodiment. Fig. 10a is a schematic cross-sectional view of the cooling equipment of a nuclear reactor in a ninth preferred embodiment of the present invention. The enlarged oblique view of the LPFL sprayer in Figure 10a. ^ -------- t --------- < Please read the notes on the back before filling this page) Applicable to China National Standard (CN.S) A4 (210 X 297 cm) 462063 ^ 7186pif.doc / 008 V. Description of the invention (<) Figure lla shows the tenth preferred embodiment of the present invention. A longitudinal cross-sectional view of a part of the cooling equipment of the nuclear reactor. The lib diagram is a top view of the lla diagram. The 12th diagram is a system diagram of the nuclear reactor cooling equipment of the eleventh preferred embodiment of the present invention. FIG. 13 shows a cooling device for a nuclear reactor in a twelfth preferred embodiment of the present invention and illustrates the present invention. System diagram of operation method of nuclear reactor cooling equipment of the first preferred embodiment. Fig. 14 shows a system diagram of operation method of nuclear reactor cooling equipment of the second preferred embodiment of the present invention. Fig. 15 shows This is a system diagram of the cooling method of the nuclear reactor cooling equipment according to the third preferred embodiment of the present invention. Figure 16 shows a system diagram of the conventional nuclear reactor cooling equipment. The marking of the diagram is as follows: 1: Pressure tank of the nuclear reactor 2: Furnace core 3: Inner pump 4: Nuclear reactor well 5: Fuel pool 6: Pool valve 7: Clearance tank 8: Fuel pool cooling and purification system pipeline 9: Inlet stop valve 10: Fuel pool cooling and purification system pump- -------------- II (Please read the notes on the back before filling out this page) This paper size is applicable to the China National Standard (CNS) Al specification (210 χ 297 mm) 4 6 2 0 6 3

AT 7 18 6pif. doc/〇 〇 8 _ _13/ _ 五、發明說明(11〇 11 :燃料池冷卻淨化系統過濾除氯裝置 12 :出口停止閥 Π:燃料池冷卻淨化系統熱交換器 14 ’ 58 :側管閥 is :燃料池冷卻淨化系統側管管路 16 :抑制池淨化系統管路 17 :燃料池循環管路 18,80,81,82 :防止逆流閥 19 :燃料池冷卻淨化系統循環水注入管路 20 :循環水注入口 21,27a,27b,27c,32,33,34,34a,34b,39,43, 44 ’ 49,50,53,55,56,62,77,79,90,95,101 : 停止閥 22 :燃料池冷卻淨化系統,核反應爐井連接管路 23 :核反應爐殘留熱去除系統之(a)系統管路 24 :核反應爐殘留熱去除系統之(B或C)系統管路 25 :核反應爐殘留熱去除系統泵 26 :核反應爐殘留熱去除系統熱交換器 28 :燃料池冷卻淨化系統-核反應爐殘留熱去除系統 連接管路 29 :核反應爐殘留熱去除系統-燃料池冷卻淨化系統 連接管路 3〇 ·核皮應爐殘留熱去除系統循環水注入口 31 :核反應爐殘留熱去除系統循環水注入管路 ------ ^ ------I — — — — — — — (請先閱讀背面之注意事項再填寫本頁) 本紙張尺度適用中國國家標準(CNS)A4規格(210 297公埜) 462063 7186pif.doc/008 … __B/_ 五、發明說明(η) 35 :核反應爐給水系統 36 :低壓注水系統噴霧器 37 :給水噴霧器 38,52 :分岐管 40 :作業地面高度 41 :冷卻水 42 :液面 45 :低壓注水系統噴霧管路 46 :第一給水噴霧管路 47 :第二給水噴霧管路 48 :匯流點 51 :燃料池冷卻淨化系統循環水流通管路 54 :核反應爐殘留熱去除系統過濾除氯裝置 57 :核反應爐殘留熱去除系統過濾除氯裝置側管 59 :核反應爐井取水管路 60 :核反應爐井上取水口 61 :間隙調壓槽取水管路 63 :核反應爐井噴霧器 64 :連接部位 65 :核反應爐井角落部位 66 :突出堤 67 :中心線 68 :遮蔽裝置 69 :側板 20 本紙張尺度適用中國國家標準(CNS)A丨規格(21〇χ 297公釐) κ·ί----- 訂 --------線 (請先閱讀背面之注意事項再填寫本頁) 4 6 2 0 6 3 A7 7166pif.doc/008 ^ __13/ _ 五、發明說明(〇 ) 70 :噴霧器噴嘴 71 :吹出口 72 :燃料池內構造物 73 :垂直配管 74 :擴散器 75 :冷卻水吹出口 76 :核反應爐冷卻材料淨化系統 78 :核反應爐冷卻材料淨化系統管路 83 :給水系統停止閥 84 :具強制驅動功能之停止閥 85 :核反應爐格納槽 86 :核反應爐冷卻材料淨化系統再生熱交換器 87 :核反應爐冷卻材料淨化系統非再生熱交換器 88 :核反應爐冷卻材料淨化系統泵 89 :核反應爐冷卻材料淨化系統過濾除氯裝置 91 :核反應爐冷卻材料淨化系統側管管路 92 :核反應爐冷卻材料淨化系統側管閥 93 :核反應爐冷卻材料淨化系統循環管路 94 :核反應爐殘留熱去除系統熱交換器連接管路 96 :核反應爐殘留熱去除系統防止逆流閥 97 :熱交換器出口側停止閥 98 :核反應爐殘留熱去除系統熱交換器側管管路 99 :側管閥 100 :放射性廢棄物處理系統連接管路 (請先閱讀背面之注意事項再填寫本頁) --------線| 本紙張尺度適用中國國家標準(CNS)A4規格<210 X 297公髮) 4 6 20 63 A/ 7186pif.d〇c/008 B7 五、發明說明(β) 102 :放射性廢棄物處理設備 103 :第一切換閥 104 :第一切換管路 105 :第二切換閥 106 :第二切換管路 較佳實施例之詳細說虹 第1圖係說明本發明之申請專利範圍第1項之第一較 佳實施例之核反應爐冷卻設備。 在第1圖中,與第16圖相同之部分係使用相同之符 號表示,在此省略重複部分的說明。本發明之第一較佳實 施例與習知例子之差異點,係爲燃料池循環管路17之下 游側與核反應爐殘留熱去除系統-燃料池冷卻淨化系統連 接管路29之下游側之連接處的匯流點48,在此匯流點48 與燃料池冷卻淨化系統循環水注入管路19分歧連接。又 燃料池循環管路17設有停止閥49,另外,自燃料池循環 管路17之防止逆流閥18之出口側分歧,且經由停止閥50 而與燃料池冷卻淨化系統循環水流通管路51相連接,此 燃料池冷卻淨化系統循環水流通管路51與核反應爐殘留 熱去除系統循環水注入管路31相連接。 即,本較佳實施例係由,利用燃料池冷卻淨化系統過 濾除氯裝置11洗淨且利用燃料池冷卻淨化系統熱交換器 13冷卻的冷卻水,經由燃料池循環管路17、燃料池冷卻 淨化系統循環水流通管路51及核反應爐殘留熱去除系統 循環水注入管路31循環至核反應爐井4的配管系統,以 22 本紙張尺度適用中國國家標準(CNSM4規格(210 * 297公餐) (請先閱讀背面之注f項再填寫本頁) ^--------訂---------線— ------------------------ 4 620 6 3 7186pif.d〇c/〇〇8 B„ _ 五、發明說明(;n> ) 及利用核反應爐殘留熱去除系統管路23、24冷卻之冷卻 水經由核反應爐殘留熱去除系統-燃料池冷卻淨化系統連 接管路29至燃料池冷卻淨化系統循環水注入管路19獨立 循環至燃料池5的配管系統所構成。 在本較佳實施例中,燃料池冷卻淨化系統與核反應爐 殘留熱去除系統匯流之匯流點48之配管係爲垂直構造’ 將燃料池冷卻淨化系統與核反應爐殘留熱去除系統之冷卻 水匯流,以進行燃料池冷卻淨化系統循環至核反應爐井4 及核反應爐殘留熱去除系統循環至燃料池5的運轉。如此’ 循環至核反應爐井4之冷卻水已經受到燃料池冷卻淨化系 統之過濾除氯裝置11淨化處理,而不會在核反應爐井4 處發生覆蓋堆積,以大幅降低受放射線感染之劑量。 另一方面,由去除破壞熱之觀點來看,在核反應爐井 4與燃料池5之間設置開放式的池閥6,以防止進行核反 應爐井4或燃料池5的兩方面冷卻時,同時進行整體的除 熱。此時,核反應爐殘留熱去除系統由核反應爐壓力槽1 中吸入至第1圖中的2系統中,1系統係來自核反應爐壓 力槽1,另一系統則來自燃料池5。 又,在第1圖中,燃料池冷卻淨化系統之取水側與連 接配置於燃料池5及核反應爐井4的間隙調壓槽7相連接 所構成。燃料池5及核反應爐井4的水溢出而流入間隙調 壓槽7中,燃料池冷卻淨化系統之水源並不直接經由燃料 池5及核反應爐井4。但,本較佳實施例實際上並不限定 燃料池冷卻淨化系統之取水側之形狀,也可以在燃料池5 23 本紙張又度適用中國國家標準(CNS)A‘丨規格(210 X 297公蜚) ------------- ^------ - 訂!! 線 (請先閱讀背面之注意事項再填寫本頁) 462063 A7 7 1 8 6pi f * doc / 0 0 8 五、發明說明(·>ρ 或核反應爐井4之上部設置燃料池冷卻淨化系統之取水 口,以直接由燃料池5或核反應爐井4中取水。或者’也 可以將燃料池冷卻淨化系統之取水口設於核反應爐井4之 底部,活用如第1圖中細線所表示之燃料池冷卻淨化系統 -核反應爐井連接管路22以對燃料池冷卻淨化系統供水。 無論是何種情形,燃料池冷卻淨化系統之水源可由燃料池 5、核反應爐井4或兩者皆有所構成。 第2圖係說明本發明之申請專利範圍第2項之第二較 佳實施例之核反應爐冷卻設備。 在第2圖中,與第1圖相同之部分係使用相同之符號 表示,在此省略重複部分的說明。本發明之第二較佳實施 例與第一較佳實施例之差異點,係爲核反應爐殘留熱去除 系統-燃料池冷卻淨化系統連接管路29與核反應爐殘留熱 去除系統循環注入管路31相連接處’設有具第一切換閥 103之第一切換管路104。又,在核反應爐殘留熱去除系 統-燃料池冷卻淨化系統連接管路29與第一切換管路104 連接處至匯流點48之間設有第二切換閥1〇5 ^ 在本較佳實施例中,核反應爐殘留熱去除系統管路 23、24之冷卻水在第一切換閥103關閉、第二切換閥105 開啓之情形下經由燃料池冷卻淨化系統循環水注入管路 19,再由循環水注入口 20循環至燃料池5中。又,在第 一切換閥103開啓、第二切換閥1〇5關閉之情形下核反應 爐殘留熱去除系統管路23、24之冷卻水則循環至核反應 爐井4中。 24 — II ."!— 訂---I----線- (請先間讀背面之注意事項再填寫本頁) 本紙張尺度適用中國國家標準(CNS)A·丨規格(210 X 297公坌) Λ7 4 6206 3 7186pif.doc/008 五、發明說明(:Λ) 第3圖係說明本發明之第二較佳實施例之其他形式之 核反應爐冷卻設備。 在第3圖中,與第1圖相同之部分係使用相同之符號 表示,在此省略重複部分的說明。在此例中,在燃料池循 環管路17上設置第二切換管路106,其中一端分歧連接安 裝有防止逆流閥18之燃料池循環管路17之進口側’另一 端連接安裝有停止閥50之燃料池冷卻淨化系統循環水流 通管路51。 在此例之中,燃料池冷卻淨化系統管路8的冷卻水先 經由燃料池循環管路17,再經由第二切換管路1〇6、停止 閥50、燃料池冷卻淨化系統循環水注入管路51及核反應 爐殘留熱去除系統循環水注入口 30循環至核反應爐井4。 此時,防止逆流閥18及停止閥49之開關狀態係爲關閉狀 態,以防止由核反應爐殘留熱去除系統管路23、24來的 含有包層之冷卻水流入核反應爐井4中。 第4圖係說明本發明之申請專利範圍第3項之第三較 佳實施例之核反應爐冷卻設備。 在第4圖中,與第1圖相同之部分係使用相同之符號 表示,在此省略重複部分的說明。本發明之第三較佳實施 例與第一較佳實施例之差異點,係爲在多系統之核反應爐 殘留熱去除系統管路之中連接設置於核反應爐壓力槽內的 低壓注水系統噴霧器,且第一或第二系統與設置於核反應 爐壓力槽內的給水噴霧器及前述低壓注水系統噴霧器相連 接。 25 本纸張尺度適用中國國家標準(CNS)A.丨規格(2丨0 X 297公釐) ----^----I---^--------線- (請先閱讀背面之注意事項再填寫本頁> 4 620 6 3 A7 7lS6pif . doc/ 0 0 8 五、發明說明(乃) 即,設置由核反應爐殘留熱去除系統之(A)系統管 路23分歧且與第一給水噴霧管路46連接之具有停止閥39 之分歧管38,以及設置由核反應爐殘留熱去除系統之(B 或C)系統管路24分歧且與第二給水噴霧管路47連接之 具有停止閥53之分歧管52。另外由核反應爐殘留熱去除 系統之(B或C)系統管路24供應低壓注水系統噴霧管路 45與第二給水噴霧管路47之核反應爐殘留熱去除系統之 冷卻水。 核反應爐殘留熱去除系統在前述中係設有3系統,習 知是核反應爐殘留熱去除系統之1系統與給水系統(核反 應爐給水系統)之局部系統相連接,由局部系統的給水噴 霧器37循環至核反應爐壓力槽1中。在1系統中有3個 給水噴霧器37,合計2系統中設置有6個,在1系統中有 1個低壓注水系統噴霧器36,合計設置有2個。但,由低 壓注水系統噴霧器36循環之冷卻水與由給水噴霧器37循 環之冷卻水比較其運轉方法,會降低核反應爐壓力槽1內 的流速,並降低其作業性。 在本實施例中,係由1系統之核反應爐殘留熱去除系 統連接給水系統(核反應爐給水系統)2系統所構成,或 由2系統之核反應爐殘留熱去除系統連接給水系統2系統 所構成,在核反應爐壓力槽1內的流速較慢、核反應爐殘 留熱去除系統冷卻水進行運轉循環至核反應爐壓力槽1之 情形下,可在不對作業性產生負面的影響下,同時具有去 除破壞熱與提升作業性之優點。 26 本紙張尺度適用中國國家標準(CN.S)A.丨规格(2]0 X 297公g ) (請先閱讀背面之注意事項再填寫本頁) -衣--------^---------線. 經濟部智慧財產局員工消費合作i£印別Λ 462063 Λ7 718 6p i f. doc /0 0 8 B7 五、發明說明 第5圖係說明本發明之申請專利範圍第6項之第四較 佳實施例之核反應爐冷卻設備。 在第5圖中,與第1圖相同之部分係使用相同之符號 表示,在此省略重複部分的說明。本發明之第四較佳實施 例係在第一較佳實施例中的核反應爐殘留熱去除系統之 (A)系統管路23及核反應爐殘留熱去除系統之(B或C) 系統管路24的核反應爐殘留熱去除系統熱交換器26之冷 卻水出口側支配管系統中設置介於停止閥55、56之間的 過濾除氯裝置54。又’在停止閥55、56之前後設置有核 反應爐殘留熱去除系統過濾除氯裝置54側管之具有側管 閥58之核反應爐殘留熱去除系統過濾除氯裝置側管57。 使用核反應爐殘留熱去除系統過濾除氯裝置54時關閉側 管閥58。 在本較佳實施例中,設有核反應爐殘留熱去除系統過 濾除氯裝置54去除核反應爐殘留熱去除系統的冷卻水中 的放射性物質,已淨化冷卻水’如此在循環至核反應爐井 4時,可在降低核反應爐井4的受放射線污染的劑量之同 時,器除破壞熱。又’核反應爐殘留熱去除系統過'濾除氯 裝置54的代用品可改設爲中空系膜過濾器等的過濾器。 又,當核反應爐殘留熱去除系統冷卻水中的放射能較低之 情形下,可開啓側管閥58,以直接經由核反應爐殘留熱去 除系統過濾除氯裝置側管閥58而通過° 第6圖係說明本發明之申請專利範圍第4項之第五較 佳實施例之核反應爐冷卻設備° 27 I ^--------^ <ίίι— . {請先間讀背面之泫意事項再填寫本頁) 本紙張尺度適用中國國家標準(CNS)iVl規格(210x297公# ) 462063 7186pif. doc/008 五、發明說明(#) 在第6圖中,與第1圖相同之部分係使用相同之符號 表示,在此省略重複部分的說明。本發明之第五較佳實施 例與第一較佳實施例之差異點,係爲由燃料池5通過間隙 調壓槽7取水後,先利用燃料池冷卻淨化系統管路8的燃 料池冷卻淨化系統過濾除氯裝置Η淨化燃料池水,再利 用燃料池冷卻淨化系統熱交換器U冷卻,之後通過燃料 池循環管路17及燃料池冷卻淨化系統循環水注入管路19 循環至燃料池5中。 又,在核反應爐壓力槽內的爐水或燃料池水受核反應 爐殘留熱去除系統冷卻,再循環至燃料池5中。此時1系 統的核反應爐殘留熱去除系統係將利用核反應爐殘留熱去 除系統熱交換器26冷卻之冷卻水循環至給水噴霧器37。 燃料池循環管路17上之防止逆流閥18與停止閥49係爲 串連連接。 在本較佳實施例中,核反應爐壓力槽1內的循環水流 速降低,會減少核反應爐井4之感染放射線劑量及提升核 反應爐壓力槽1內之燃料交換的遠隔通路作業性。又循環 至給水噴霧器37之流量係受到核反應爐壓力槽1內的流 速所限制,較佳的核反應爐殘留熱去除系統管路的流量約 爲50%程度。 第7圖係說明本發明之申請專利範圍第5項之第六較 佳實施例之核反應爐冷卻設備。 在第7圖中,與第16圖相同之部分係使用相同之符 號表示,在此省略重複部分的說明°本發明之第六較佳實 28 本紙張尺度適用中國國家標準(CNS)A!規格(210><297公餐) ^--------訂·-----|!線| (讀先閲讀背面之注意事項再填寫本頁) :62063 7186pif.doc/008 Λ7 B7 五、發明說明(>t) 施例與習知例之差異點,係爲核反應爐殘留熱去除系統之 (A)系統管路23或核反應爐殘留熱去除系統之(B或C) 系統管路24與核反應爐井取水管路59相連接,此核反應 爐井取水管路59之上端部分安裝有核反應爐井上部取水 口 60。又由間隙調壓槽7連接於燃料池冷卻淨化系統管路 8之進口停止閥9之上游側分歧處與間隙調壓槽取水管路 61之一端相連接,此間隙調壓槽取水管路61之另一端經 由停止閥62與核反應爐殘留熱去除系統之(A)系統管路 23或核反應爐殘留熱去除系統之(B或C)系統管路24 相連接。 在間隙調壓槽7內係爲燃料池5之上部水’且係自工 作地面流入乾淨的上澄水。經核反應爐破壞熱之自然對流 造成核反應爐井4之上部具高溫。因此,在本較佳實施例 之中,利用核反應爐殘留熱去除系統管路23或24所連接 的核反應爐井上部取水口 60取得核反應爐井4的上部水, 或利用間隙調壓槽取水管路61取得燃料池5的上部水, 如此之上部水經由核反應爐殘留熱去除系統管路23或24 的核反應爐殘留熱去除系統熱交換器26冷卻之後,在循 環至核反應爐井4中。 在本較佳實施例中,核反應爐井4之上部及燃料池5 之上部的水質比爐水較無包層,以降低核反應爐井4的受 放射線污染劑量。又,核反應爐殘留熱去除系統管路所循 環的冷卻水不必要循環至核反應爐壓力槽1中,不會對遠 隔操作之作業性造成損害。 2<) (請先閱讀背面之注意事項再填寫本頁) 訂---------線— 經濟部智慧財產局員工消費合作社印製 本紙張尺度適用中國國家標準(CNS)Al規格(21〇χ 297公t ) A7 B7 462063 7186pif . doc/008 五、發明說明) 第8圖係說明本發明之申請專利範圍第7項之第七較 佳實施例之核反應爐冷卻設備。 在第8圖中所示爲第1圖至第7圖之核反應爐井4之 中心線67之左側的部分放大的槪略縱截面圖。又,符號1 係表示核反應爐壓力槽之部分,符號63係表示核反應爐 井噴霧器之槪略縱截面圖,由核反應爐井噴霧器63中的 中心點開始之箭頭方向A、B、C、D係爲核反應爐井噴霧 器63中所設定之冷卻水吹出口之吹出方向。 符號64係表示核反應爐1之上端部與核反應爐井4 之底部所安裝之防水連接材料,符號65係爲核反應爐井 角落部位,66係突出堤。核反應爐壓力槽1內儲存有爐水。 在習知例中,核反應爐井噴霧器63設有A,B,C的 方向之吹出口,冷卻水由此方向吹出之構造。但,包層匯 集中於核反應爐井角落部位65,此爲造成在移除核反應爐 井之水後的除污作業時,作業人員受到放射線感染之原 因。 因此,在本較佳實施例中,不設置盡頭朝向核反應爐 井角落部位65之正上方之B方向與盡頭朝向壁面斜下方 向之C方向的吹出口,而改設置盡頭朝向中心線67斜下 方向之A方向與盡頭朝向中心線67水平方向之D方向的 雖出口。在本較佳實施例中,係由A方向與D方向之吹 出口吹出冷卻水,以使核反應爐井4底部,特別是角落部 位65難以集中包層,以在進行反應爐井4的除污時,降 低作業人員之放射線感染。 30 本紙張尺度適用中國國家標準(CN.S)規格mo X 297公g ) I 於-------ί訂---------線- {請先閱讀背面之注意事項再填寫本頁) 462063 7186pif.doc/008 五、發明說明d) 第9圖係說明本發明之申請專利範圍第8項之第八較 佳實施例之核反應爐冷卻設備。 在第9圖中所示爲第1圖至第7圖之核反應爐井4與 核反應爐壓力槽1的部分放大的槪略縱截面圖。在第9圖 中,符號68係遮蔽裝置’ 69係側板。在本較佳實施例中’ 在設置於於核反應爐壓力槽1內之低壓注水系統噴霧器36 上方與外側包覆遮蔽裝置68。 在本較佳實施例中,利用核反應爐殘留熱去除系統之 (B或C)系統管路24冷卻之冷卻水循環至核反應爐壓力 槽1時,也循環至低壓注水系統噴霧器36 ’此時在低壓注 水系統噴霧器36上安裝遮蔽裝置68 ’使來自低壓注水系 統噴霧器36的循環水於側板69與核反應爐壓力槽之間落 下,以防止吹向核反應爐壓力槽1的中心方向。如此,藉 由限制攜入包層至核反應爐井4,可降低核反應爐井受放 射線之污染,以在不妨害遠隔操作下通入核反應爐壓力槽 之作業性的情形下,去除破壞熱。 第l〇a圖與第l〇b圖係說明本發明之申請專利範圍1第 8項之第九較佳實施例之核反應爐冷卻設備。 第10a圖所示爲與第9圖相同之核反應爐井4與核反 應爐壓力槽1的部分的槪略截面圖。第l〇b圖所示爲在第 10a圖中之LPFL噴霧器的放大斜視圖。 在本較佳實施例中,於核反應爐壓力槽1內所設 低壓注水系統噴霧器36的下面安裝有多個噴霧器 70,此噴霧器噴嘴70的冷卻水吹出口 7〗係設定爲朝向^ 本紙張尺度適用中國國家標準(CNS)A4規格(MO X 297公釐) (請先閱讀背面之注意事項再填寫本頁) ^--------訂---------線- Λ7 B7 4 620 6· 7 1 8 6pi f . doc /0 0 8 五、發明說明(d) 下方。 習知之低壓注水系統噴霧器36的噴霧器噴嘴彳系 於低壓注水系統噴霧器36的上面,經途中曲折的吹出D 冷卻水會朝向核反應爐壓力槽之中心線吹出。相&&& 點,在本較佳實施例之中,低壓注水系統之噴霧器噴@ % 係安裝於低壓注水系統噴霧器36之下面,且吹出口 71 t 方向朝下,可避免冷卻水朝向核反應爐壓力槽1之中心、1 泉 吹出。 在本較佳實施例中,核反應爐殘留熱去除系統 應爐壓力槽中循環更換燃料之方式,不會發生燃料·胃 晃問題。此時,藉由限制攜入包層至核反應爐井’ 核反應爐井受放射線之污染。又,變更噴霧器噴嘴之’ 也可以減少改造物之量。 關於第11a圖與第lib圖中係說明本發明之申請專利 範圍第9項之第十較佳實施例之核反應爐冷卻設備° 在第11a圖中所示爲第1圖至第7圖之燃料池5的放 大的槪略縱截面圖。第lib圖係爲第11a圖之上視圖。在 第11a圖與第lib圖中,符號72係爲燃料池內的構造物, 用來儲存使用過之燃料,73係爲垂直配管,74係爲連接 於垂直配管73的擴散器,75係爲設於擴散器74上的多個 小孔。 在本較佳實施例中,於燃料池5內一根垂直配管73 對應安裝上下兩根擴散器74,此垂直配管73在燃料池內 構造物72之兩側各設有一根。在擴散器74上設有多個小 32 本紙張尺度適用中國國家標準(CNS)/V丨規格(21〇 X 297公楚) ^--------^-------I 線· (請先閱讀背面之注意事項再填寫本頁) Α7 Β7 4 6 20 6 186pif.doc/008 五、發明說明(Je) 口徑的冷卻水吹出口 75以吹出冷卻水。此擴散器74的根 數並不限於4根,可隨著內容物或冷卻水的量而有所增減^ 垂直配管73係相當於第一較佳實施例之第1圖所示之燃 料池冷卻淨化系統循環水注入管路19,擴散器則相當於循 環水注入口 20。 例如在第一較佳實施例之中,大量的冷卻水必須運轉 至燃料池5中,在燃料池5內的擴散器口徑如果不大,或 許會對燃料池5內的佈局上有所不利。另一方面來說,由 燃料池5的冷卻觀點來看,燃料池5之底部最好配置有擴 散器74。 此時,由第1U圖與第lib圖所示之燃料池5之底部 之垂直配管73會隨著流量的增加而對應擴大口徑。另一 方面,在燃料池底部水平設置之擴散器74,參照第11a圖 所示係於一根垂直配管73上對應安裝上下棚段狀之兩根, 且參照第Ub圖所示係此垂直配管73在燃料池內構造物72 之兩側各設有一根。 在本較佳實施例之中,防止配管口徑之擴大,對燃料 池5內的佈局才真正有利。以在核能發電廠中,利用遠隔 離操作核反應爐壓力槽通路之情形下,以不降低作業性’ 並抑制核反應爐井之放射線以降低放射劑量,以進行破壞 熱之去除。 雖然在第11圖中之擴散器74係利用設有2跟之情形 進行說明,但也可以設置成3根以上之棚狀擴散器,此情 形時也可以得到與上述相同之效果。 33 (請先閱讀背面之注意事項再填寫本頁) ^--------訂---------線- 齊 % 讨 i f 本纸張尺度適用中國國家標準(CNSMO見格(210 X 297公釐) 4 6 20 6 3 Λ7 7186pif.doc/008 gy ____ 五、發明說明(M) 關於第12圖係說明本發明之申請專利範圍第10項之 第十一較佳實施例之核反應爐冷卻設備。 在第12圖中所示之本較佳實施例中’核反應爐壓力 槽1內的給水噴霧器37的A、B系統與核反應爐冷卻材 料淨化系統(簡稱CCUW)係經由停止閥77、核反應爐 冷卻材料淨化系統管路78、停止閥79、防止逆流閥80、81、 82及給水系統停止閥83相連接’特別在給水系統(A系 統)設置了代替防止逆流閥80之具有強制啓動機能之防 止逆流閥84。 具有強制啓動機能之防止逆流閥84與淨化水之流動 方向相反,以在必要時,強制開啓對應於流動方向之相反 方向,以表示安裝側管防止逆流閥。在第12圖中’符號85 係顯示了部分核反應爐格納槽。又’核反應爐給水系統(A 系統)係與核反應爐殘留熱去除系統之(A)系統管路分 歧連接。 在習知例中之核反應爐殘留熱去除系統之(A)系統 管路23係由給水系統35之第一給水噴霧管路46循環所 構成,而在本較佳實施例中則是設置具有強制啓動機能之 防止逆流閥84,在此防止逆流閥84強制開啓之狀態下, 來自核反應爐殘留熱去除系統之(A)系統管路23之冷卻 水可循環至核反應爐給水系統35的第一給水噴霧管路(A 系統)46及第二給水噴霧管路(B系統)47之兩方相互 循環。 在本較佳實施例中,核反應爐冷卻材料淨化系統管路 34 本纸張尺度適用中國國家標準(CNShVi規格(210 X 297公餐) 3^--------訂---------線· (請先閱讀背面之注意事項再填寫本頁) 經齊耶智慧时逢-¾員工消費合作杜印製 4 6 206 3 7186pif.doc/008 ^ __B/ 五、發明說明( 78安裝有停止閥79或給水系統停止閥83,以將來自核反 應爐冷卻材料淨化系統之冷卻水擇一循環至第一給水噴霧 管路(A系統)46或第二給水噴霧管路(B系統)47 ’並 在對核反應爐壓力槽1內的燃料交換的作業抑制至最小限 度之影響的情形下進行破壞熱之去除。AT 7 18 6pif.doc / 〇〇8 _ _13 / _ V. Description of the invention (11〇11: Fuel pool cooling and purification system filtration and chlorine removal device 12: Exit stop valve Π: Fuel pool cooling and purification system heat exchanger 14 '58 : Side pipe valve is: fuel tank cooling and purification system side pipe line 16: suppression pool purification system line 17: fuel pool circulation line 18, 80, 81, 82: anti-reverse valve 19: fuel pool cooling and purification system circulating water Injection line 20: circulating water injection ports 21, 27a, 27b, 27c, 32, 33, 34, 34a, 34b, 39, 43, 44 '49, 50, 53, 55, 56, 62, 77, 79, 90 , 95, 101: Stop valve 22: Fuel pool cooling and purification system, nuclear reactor well connection pipeline 23: (a) system pipeline of nuclear reactor residual heat removal system 24: nuclear reactor furnace residual heat removal system (B or C) System line 25: Nuclear reactor residual heat removal system pump 26: Nuclear reactor residual heat removal system heat exchanger 28: Fuel tank cooling purification system-Nuclear reactor residual heat removal system connection line 29: Nuclear reactor residual heat removal system-fuel Pool cooling and purification system connection pipe 30. Nuclear skin furnace furnace residue Circulating water injection port 31 of the heat removal system: Circulating water injection pipe of the residual heat removal system of the nuclear reactor -------- ^ ------ I — — — — — — (Please read the precautions on the back before (Fill in this page) This paper size is in accordance with Chinese National Standard (CNS) A4 specification (210 297 public field) 462063 7186pif.doc / 008… __B / _ V. Description of the invention (η) 35: Water supply system for nuclear reactor 36: Low pressure water injection system Sprayer 37: Water supply sprayer 38, 52: Manifold 40: Working floor height 41: Cooling water 42: Liquid level 45: Low-pressure water injection system spray line 46: First water supply spray line 47: Second water supply spray line 48: Convergence point 51: Circulating water circulation pipeline of the fuel pool cooling and purification system 54: Residual heat removal system of the nuclear reactor furnace filtration and dechlorination device 57: Residual heat removal system of the nuclear reactor furnace filtration and dechlorination device side pipe 59: Nuclear reactor furnace water extraction pipeline 60: Water inlet 61 on the well of nuclear reactor furnace: Water intake pipe of gap pressure regulating tank 63: Sprayer of nuclear reactor well 64: Connection site 65: Corner of nuclear reactor well 66: Protruded bank 67: Centerline 68: Shading device 69: Side plate 20 Paper size suitable China National Standard (CNS) A 丨 Specifications (21〇χ 297 mm) κ · ί ----- Order -------- Line (Please read the precautions on the back before filling this page) 4 6 2 0 6 3 A7 7166pif.doc / 008 ^ __13 / _ V. Description of the invention (〇) 70: Sprayer nozzle 71: Blowout port 72: Structure in fuel tank 73: Vertical pipe 74: Diffuser 75: Cooling water blowout port 76: Nuclear reactor cooling material purification system 78: Nuclear reactor cooling material purification system piping 83: Water supply system stop valve 84: Stop valve with forced drive function 85: Nuclear reactor furnace tank 86: Nuclear reactor cooling material purification system regenerative heat exchange Unit 87: Nuclear reactor cooling material purification system non-regenerative heat exchanger 88: Nuclear reactor cooling material purification system pump 89: Nuclear reactor cooling material purification system filtration and chlorine removal device 91: Nuclear reactor cooling material purification system side pipe line 92: Nuclear reaction Furnace cooling material purification system side pipe valve 93: Nuclear reactor cooling material purification system circulation line 94: Nuclear reactor residual heat removal system heat exchanger connection line 96: Nuclear reactor residual heat removal system prevention counterflow valve 97: Stop valve 98 on the outlet side of the exchanger: Reactor residual heat removal system heat exchanger side pipe line 99: Side pipe valve 100: Radioactive waste treatment system connection pipe (Please read the precautions on the back before filling this page)- ------- line | This paper size applies to China National Standard (CNS) A4 specifications < 210 X 297 public release) 4 6 20 63 A / 7186pif.d〇c / 008 B7 V. Description of the invention (β) 102: Radioactive waste processing equipment 103: First switching valve 104: First switching pipeline 105: Second switching valve 106: Detailed description of the preferred embodiment of the second switching pipeline Figure 1 illustrates the application of the present invention Nuclear reactor cooling equipment of the first preferred embodiment of the scope of the patent. In FIG. 1, parts that are the same as those in FIG. 16 are denoted by the same symbols, and repeated descriptions are omitted here. The difference between the first preferred embodiment of the present invention and the conventional example is the connection between the downstream side of the fuel pool circulation pipe 17 and the downstream side of the residual heat removal system-fuel pool cooling and purification system connection pipe 29 of the nuclear reactor. The confluence point 48 here is connected to the circulating water injection pipe 19 of the fuel pool cooling and purification system. The fuel pool circulation line 17 is provided with a stop valve 49. In addition, the fuel pool circulation line 17 is diverged from the exit side of the anti-reverse valve 18 of the fuel pool circulation line 17 and communicates with the fuel pool cooling and purification system circulating water circulation line 51 through the stop valve 50 Connected, the circulating water circulation pipe 51 of the fuel pool cooling and purification system is connected to the circulating water injection pipe 31 of the residual heat removal system of the nuclear reactor. That is, the present preferred embodiment uses the fuel pool cooling and purification system to filter the cooling water washed by the chlorine removal device 11 and the fuel pool cooling and purification system heat exchanger 13 to cool the cooling water through the fuel pool circulation pipe 17 and the fuel pool. Purification system circulating water circulation line 51 and nuclear reactor residual heat removal system circulating water injection line 31 circulates to the piping system of nuclear reactor well 4 and 22 paper standards are applicable to Chinese national standards (CNSM4 specification (210 * 297 meals)) (Please read the note f on the back before filling in this page) ^ -------- Order --------- Line — --------------- --------- 4 620 6 3 7186pif.d〇c / 〇〇8 B _ _ V. Description of the invention (; n >) and cooling using the nuclear reactor furnace residual heat removal system pipes 23, 24 cooling Water is independently circulated to the piping system of the fuel pool cooling and purification system circulating water injection pipe 19 through the residual heat removal system-fuel pool cooling and purification system connection pipe 29 of the nuclear reactor to the fuel pool 5. In this preferred embodiment, The piping system at the confluence point 48 of the fuel pool cooling and purification system and the nuclear reactor residual heat removal system is vertical Make 'converge the cooling water of the fuel pool cooling and purification system and the residual heat removal system of the nuclear reactor to circulate the fuel pool cooling and purification system to the nuclear reactor well 4 and the nuclear reactor residual heat removal system to the fuel pool 5. This' The cooling water circulating to the nuclear reactor well 4 has been purified by the filtering and dechlorination device 11 of the fuel pool cooling purification system without covering and accumulation in the nuclear reactor well 4 to greatly reduce the dose of radiation infection. From the viewpoint of removing destruction heat, an open-type pool valve 6 is provided between the nuclear reactor shaft 4 and the fuel pool 5 to prevent the cooling of both sides of the nuclear reactor shaft 4 or the fuel pool 5 at the same time as a whole. At this time, the residual heat removal system of the nuclear reactor is sucked from the pressure tank 1 of the nuclear reactor to 2 systems in the first figure, where 1 system is from the pressure tank 1 of the nuclear reactor, and the other system is from the fuel pool 5. In FIG. 1, the water intake side of the fuel pool cooling and purifying system is connected to the gap pressure regulating tank 7 connected to the fuel pool 5 and the nuclear reactor shaft 4. The water in the fuel pool 5 and the nuclear reactor shaft 4 overflows and flows into the gap pressure regulating tank 7. The water source of the fuel pool cooling and purification system does not directly pass through the fuel pool 5 and the nuclear reactor shaft 4. However, this preferred embodiment actually does not It is not limited to the shape of the water intake side of the fuel pool cooling and purification system. It can also be used in the fuel pool 5 23 This paper is also applicable to China National Standard (CNS) A '丨 size (210 X 297 cm) -------- ----- ^ -------Order !!! (Please read the notes on the back before filling in this page) 462063 A7 7 1 8 6pi f * doc / 0 0 8 V. Description of the invention (· > ρ or the upper part of the nuclear reactor shaft 4 is provided with a water inlet of the fuel pool cooling and purification system to directly take water from the fuel pool 5 or the nuclear reactor shaft 4. Or 'You can also set the water intake of the fuel pool cooling and purification system at the bottom of the nuclear reactor well 4 and use the fuel pool cooling and purification system-nuclear reactor well connection pipe 22 as shown by the thin line in Figure 1 to cool the fuel pool. Water purification system. In any case, the water source of the fuel pool cooling and purification system can be composed of the fuel pool 5, the nuclear reactor shaft 4, or both. Fig. 2 illustrates the nuclear reactor cooling equipment of the second preferred embodiment of item 2 of the patent application scope of the present invention. In Fig. 2, the same parts as those in Fig. 1 are denoted by the same reference numerals, and duplicated explanations are omitted here. The difference between the second preferred embodiment of the present invention and the first preferred embodiment is the connection line 29 for the residual heat removal system of the nuclear reactor-fuel pool cooling purification system and the circulation injection line 31 for the residual heat removal system of the nuclear reactor. A first switching line 104 having a first switching valve 103 is provided at the connection point. In addition, a second switching valve 105 is provided between the connection line 29 between the residual heat removal system of the nuclear reactor and the fuel pool cooling and purification system and the connection point between the first switching line 104 and the junction point 48. In the preferred embodiment, In the case, the cooling water of the residual heat removal system pipelines 23 and 24 of the nuclear reactor is injected into the pipeline 19 through the fuel pool cooling and purification system when the first switching valve 103 is closed and the second switching valve 105 is opened. The injection inlet 20 is circulated to the fuel pool 5. In addition, when the first switching valve 103 is opened and the second switching valve 105 is closed, the cooling water in the nuclear reaction furnace residual heat removal system pipes 23 and 24 is circulated to the nuclear reaction furnace shaft 4. 24 — II. &Quot;! — Order --- I ---- line- (Please read the precautions on the back before filling in this page) This paper size applies to China National Standard (CNS) A · 丨 specifications (210 X 297 cm) Λ7 4 6206 3 7186pif.doc / 008 V. Description of the Invention (: Λ) Figure 3 illustrates other forms of nuclear reactor cooling equipment in the second preferred embodiment of the present invention. In Fig. 3, the same parts as those in Fig. 1 are denoted by the same reference numerals, and duplicated descriptions are omitted here. In this example, a second switching line 106 is provided on the fuel pool circulation line 17, one end of which is connected to the inlet side of the fuel pool circulation line 17 provided with a backflow prevention valve 18, and the other end is connected with a stop valve 50. Circulating water circulation line 51 of the fuel pool cooling and purifying system. In this example, the cooling water of the fuel pool cooling and purifying system pipeline 8 passes through the fuel pool circulating pipeline 17 first, and then through the second switching pipeline 106, the stop valve 50, and the fuel pool cooling and purification system circulating water injection pipeline. 51 and the circulating water injection port 30 of the residual heat removal system of the nuclear reactor are circulated to the nuclear reactor shaft 4. At this time, the switching states of the counterflow valve 18 and the stop valve 49 are closed to prevent the cooling water containing the cladding from the nuclear reactor furnace residual heat removal system pipes 23, 24 from flowing into the nuclear reactor shaft 4. Fig. 4 illustrates the nuclear reactor cooling equipment of the third preferred embodiment of item 3 of the patent application scope of the present invention. In Fig. 4, the same parts as those in Fig. 1 are denoted by the same reference numerals, and duplicated explanations are omitted here. The difference between the third preferred embodiment of the present invention and the first preferred embodiment is that the low-pressure water injection system sprayer installed in the pressure tank of the nuclear reactor is connected to the multi-system nuclear reactor furnace residual heat removal system pipeline. And the first or second system is connected with the water supply sprayer and the aforementioned low pressure water injection system sprayer arranged in the pressure tank of the nuclear reactor. 25 This paper size applies to China National Standard (CNS) A. 丨 Specifications (2 丨 0 X 297 mm) ---- ^ ---- I --- ^ -------- line-( Please read the precautions on the back before filling in this page> 4 620 6 3 A7 7lS6pif .doc / 0 0 8 V. Description of the invention (that is,) (A) system piping set up by a nuclear reactor residual heat removal system 23 A branch pipe 38 having a stop valve 39 and a branch pipe 38 provided with a stop valve 39 connected to the first feed water spray pipe 46 and a branch (B or C) system pipe 24 provided with a residual heat removal system of the nuclear reactor and branched to the second feed water spray pipe 47 The connected branch pipe 52 with a stop valve 53. In addition, the (B or C) system pipe 24 of the residual heat removal system of the nuclear reactor is supplied with the low-pressure water injection system spray pipe 45 and the second feed water spray pipe 47 of the nuclear reactor residual heat The cooling water of the removal system. The residual heat removal system of the nuclear reactor is provided with 3 systems. It is known that the 1st system of the residual heat removal system of the nuclear reactor is connected to the local system of the water supply system (nuclear reactor furnace water supply system). The system's feed sprayer 37 is circulated to the nuclear reactor pressure tank 1. In the 1 system There are 3 water-supply sprayers 37 in total, 6 in 2 systems, 1 low-pressure water injection system sprayer 36 in system 1, and 2 in total. However, the cooling water circulating by the low-pressure water injection system sprayer 36 and the Compared with the operating method of the cooling water circulating by the water supply sprayer 37, the flow velocity in the pressure tank 1 of the nuclear reactor is reduced, and the workability is reduced. In this embodiment, the residual heat removal system of the nuclear reactor 1 is connected to the water supply system ( Nuclear reactor furnace water supply system) 2 systems, or a system 2 nuclear reactor furnace residual heat removal system connected to the water supply system 2 system, the flow velocity in the nuclear reactor pressure tank 1 is slow, and the nuclear reactor furnace residual heat removal system cooling water is performed In the case where the operation cycle is to the pressure tank 1 of the nuclear reactor, it has the advantages of removing the destruction heat and improving the workability without negatively affecting the workability. 26 This paper size is applicable to the Chinese National Standard (CN.S) A.丨 Specifications (2) 0 X 297g g) (Please read the precautions on the back before filling this page) -Clothing -------- ^ --------- line. Intellectual Property of the Ministry of Economic Affairs Board member Consumption cooperation i Indo Λ 462063 Λ 7 718 6p i f. Doc / 0 0 8 B7 V. Description of the invention Fig. 5 illustrates the nuclear reactor cooling equipment of the fourth preferred embodiment of item 6 of the scope of patent application of the present invention In FIG. 5, the same parts as those in FIG. 1 are denoted by the same symbols, and repeated descriptions are omitted here. The fourth preferred embodiment of the present invention is a nuclear reactor in the first preferred embodiment. (A) system pipe 23 of the residual heat removal system and (B or C) system heat pipe of the nuclear reactor furnace residual heat removal system (B or C) system pipe 24 are installed in the cooling water outlet side branch pipe system of the heat exchanger 26 A filtering and removing device 54 between the stop valves 55 and 56. In addition, before and after the stop valves 55 and 56 are installed, a nuclear reactor furnace residual heat removal system has a side tube valve 58 of a nuclear reactor furnace residual heat removal system filtering and dechlorinating device 54 having a side pipe valve 58. When the residual heat removal system of the nuclear reactor is used to filter the chlorine removal device 54, the side pipe valve 58 is closed. In this preferred embodiment, a nuclear reactor furnace residual heat removal system filtering and dechlorination device 54 is provided to remove radioactive materials in the cooling water of the nuclear reactor furnace residual heat removal system. The purified cooling water is thus circulated to the nuclear reactor furnace shaft 4, It is possible to reduce the radiation-contaminated dose of the nuclear reactor shaft 4 while removing the destruction heat. The substitute for the chlorine removal and removal device 54 of the residual heat removal system of the nuclear reactor can be changed to a filter such as a hollow membrane filter. In addition, when the radiant energy in the cooling water of the residual heat removal system of the nuclear reactor is low, the side tube valve 58 may be opened to pass through the side tube valve 58 of the chlorine removal device of the nuclear reactor by filtering the residual heat removal system. This is the fifth preferred embodiment of the nuclear reactor cooling equipment for explaining the fifth preferred embodiment of the scope of patent application of the present invention ° 27 I ^ -------- ^ < ίί—. {Please read the intention on the back first Please fill in this page again for this matter) This paper size is in accordance with Chinese National Standard (CNS) iVl specification (210x297 public #) 462063 7186pif. Doc / 008 5. Description of the invention (#) In Figure 6, the same parts as in Figure 1 are The same symbols are used, and repeated descriptions are omitted here. The difference between the fifth preferred embodiment of the present invention and the first preferred embodiment is that after the water is taken from the fuel pool 5 through the gap pressure regulating tank 7, the fuel pool cooling and purification system pipeline 8 is first used for cooling and purification. The system filters the chlorine removal device to purify the fuel pool water, and then uses the fuel pool cooling and purification system heat exchanger U to cool it, and then circulates to the fuel pool 5 through the fuel pool circulation pipeline 17 and the fuel pool cooling and purification system circulation water injection pipeline 19. Furthermore, the furnace water or fuel pool water in the pressure tank of the nuclear reactor is cooled by the residual heat removal system of the nuclear reactor and recycled to the fuel pool 5. At this time, the residual heat removal system of the nuclear reactor of the first system circulates the cooling water cooled by the heat exchanger 26 of the nuclear reactor residual heat removal system to the feed water sprayer 37. The anti-backflow valve 18 and the stop valve 49 on the fuel pool circulation line 17 are connected in series. In the present preferred embodiment, the reduction of the circulating water flow rate in the pressure tank 1 of the nuclear reactor will reduce the dose of infection radiation in the well 4 of the nuclear reactor and improve the operability of the remote access to the fuel exchange in the pressure tank 1 of the nuclear reactor. The flow rate circulated to the feed water sprayer 37 is limited by the flow rate in the pressure tank 1 of the nuclear reactor, and the flow rate of the pipe of the residual heat removal system of the preferred nuclear reactor is about 50%. Fig. 7 illustrates the nuclear reactor cooling equipment of the sixth preferred embodiment of item 5 of the patent application scope of the present invention. In FIG. 7, the same parts as those in FIG. 16 are denoted by the same symbols, and repeated descriptions are omitted here. The sixth preferred embodiment of the present invention 28 The paper size applies the Chinese National Standard (CNS) A! (210 > &297; Meal) ^ -------- Order · ----- |! Line | (Read the precautions on the back before filling in this page): 62063 7186pif.doc / 008 Λ7 B7 V. Description of the invention (> t) The difference between the examples and the conventional examples is the (A) system pipe 23 of the nuclear reactor residual heat removal system or the (B or C) system of the nuclear reactor residual heat removal system The pipeline 24 is connected to the nuclear reactor furnace water intake pipeline 59, and the upper end portion of the nuclear reactor furnace water intake pipeline 59 is installed with a nuclear reactor furnace upper water intake 60. The gap regulating tank 7 is connected to the upstream side of the inlet stop valve 9 of the fuel pool cooling and purifying system pipe 8 and is connected to one end of the gap regulating tank water intake pipe 61. The gap regulating tank water intake pipe 61 The other end is connected to the (A) system pipeline 23 of the nuclear reactor residual heat removal system or the (B or C) system pipeline 24 of the nuclear reactor residual heat removal system via a stop valve 62. Inside the gap pressure regulating tank 7 is the upper water 'of the fuel pool 5, and clean upper water flows from the working floor. The natural convection of the heat is destroyed by the nuclear reactor, causing the upper part of the nuclear reactor shaft 4 to have a high temperature. Therefore, in the preferred embodiment, the upper water inlet 60 of the nuclear reactor well is connected to the nuclear reactor furnace upper water intake 60 connected to the nuclear reactor furnace residual heat removal system pipe 23 or 24, or the gap pressure regulating tank water intake pipe is used. The path 61 obtains the upper water of the fuel pool 5, so that the upper water is cooled through the nuclear reactor residual heat removal system pipe 23 or 24 of the nuclear reactor residual heat removal system heat exchanger 26 and then circulated to the nuclear reactor shaft 4. In the preferred embodiment, the water quality of the upper part of the nuclear reactor shaft 4 and the upper part of the fuel pool 5 is less cladding than the boiler water, so as to reduce the radiation contamination dose of the nuclear reactor shaft 4. In addition, the cooling water circulating through the piping of the residual heat removal system of the nuclear reactor is not necessarily circulated to the pressure tank 1 of the nuclear reactor, and it will not cause damage to the operability of remote operation. 2 <) (Please read the notes on the back before filling in this page) Order --------- line — printed by the Consumers ’Cooperative of the Intellectual Property Bureau of the Ministry of Economic Affairs This paper applies the Chinese National Standard (CNS) Al specification (21〇χ297297t) A7 B7 462063 7186pif.doc / 008 V. Description of the invention Figure 8 illustrates the nuclear reactor cooling equipment of the seventh preferred embodiment of item 7 of the scope of patent application of the present invention. Fig. 8 is an enlarged vertical sectional view of a part to the left of the center line 67 of the nuclear reactor shaft 4 of Figs. 1 to 7. In addition, reference numeral 1 indicates a part of the pressure tank of the nuclear reactor, and reference numeral 63 indicates a schematic longitudinal sectional view of the nuclear reactor well sprayer. The directions A, B, C, and D from the center point in the nuclear reactor well sprayer 63 are shown. This is the blowing direction of the cooling water blowing port set in the nuclear reactor well sprayer 63. The symbol 64 is a waterproof connection material installed at the upper end of the nuclear reactor 1 and the bottom of the nuclear reactor shaft 4, the symbol 65 is a corner portion of the nuclear reactor shaft, and 66 is a protruding bank. Furnace water is stored in the nuclear reactor pressure tank 1. In the conventional example, the nuclear reactor well sprayer 63 is provided with blowout ports in the directions of A, B, and C, and cooling water is blown out in this direction. However, the cladding sinks are concentrated in the corner 65 of the nuclear reactor well, which is the cause of radiation infection in the workers during decontamination after removing the water from the nuclear reactor well. Therefore, in the present preferred embodiment, the blowout port with the end point facing the direction B above the corner 65 of the nuclear reactor well and the direction C where the end point faces the oblique downward direction of the wall is not provided, and the end point is obliquely directed downward toward the center line 67. The exits of the direction A and the direction D whose end points toward the horizontal direction of the center line 67 are exits. In the present preferred embodiment, cooling water is blown out from the blowing outlets in the A and D directions, so that the bottom of the nuclear reactor well 4, especially the corner 65, is difficult to concentrate the cladding, in order to perform the decontamination of the reactor well 4. To reduce the radiation infection of workers. 30 This paper size applies the Chinese National Standard (CN.S) specification mo X 297g g) I in --------- Order --------- line-{Please read the notes on the back first Fill out this page again) 462063 7186pif.doc / 008 V. Description of the invention d) Figure 9 illustrates the nuclear reactor cooling equipment of the eighth preferred embodiment of the eighth preferred embodiment of the scope of patent application of the present invention. Fig. 9 is a partially enlarged vertical sectional view of the nuclear reactor shaft 4 and the nuclear reactor pressure tank 1 in Figs. 1 to 7. In Fig. 9, reference numeral 68 is a shielding device '69 is a side plate. In this preferred embodiment, a shielding device 68 is covered above and outside the low-pressure water injection system sprayer 36 provided in the pressure tank 1 of the nuclear reactor. In this preferred embodiment, when the cooling water cooled by the (B or C) system pipe 24 of the residual heat removal system of the nuclear reactor is circulated to the pressure tank 1 of the nuclear reactor, it is also circulated to the low-pressure water injection system sprayer 36 ' The water injection system sprayer 36 is provided with a shielding device 68 ′, so that the circulating water from the low-pressure water injection system sprayer 36 falls between the side plate 69 and the nuclear reactor pressure tank to prevent it from blowing toward the center of the nuclear reactor pressure tank 1. In this way, by limiting the carrying of the cladding to the nuclear reactor shaft 4, the radiation contamination of the nuclear reactor shaft can be reduced to remove the heat of destruction without impairing the operability of accessing the nuclear reactor pressure tank under remote operation. Figures 10a and 10b illustrate the nuclear reactor cooling equipment of the ninth preferred embodiment of the eighth item of the scope of patent application 1 of the present invention. Fig. 10a is a schematic cross-sectional view of a portion of the nuclear reactor shaft 4 and the nuclear reactor pressure tank 1 which is the same as that shown in Fig. 9. Figure 10b shows an enlarged perspective view of the LPFL sprayer in Figure 10a. In the preferred embodiment, a plurality of sprayers 70 are installed below the sprayer 36 of the low-pressure water injection system provided in the pressure tank 1 of the nuclear reactor, and the cooling water blowing outlet 7 of the sprayer nozzle 70 is set to face the paper size. Applicable to China National Standard (CNS) A4 specification (MO X 297 mm) (Please read the precautions on the back before filling this page) ^ -------- Order --------- Line- Λ7 B7 4 620 6 · 7 1 8 6pi f. Doc / 0 0 8 V. The description of the invention (d). The sprayer nozzle of the conventional low-pressure water injection system sprayer 36 is attached to the upper surface of the low-pressure water injection system sprayer 36, and the tortuous blowout D cooling water will blow toward the center line of the pressure tank of the nuclear reactor. At the point of & & &, in the preferred embodiment, the sprayer spray of the low-pressure water injection system @% is installed below the low-pressure water injection system sprayer 36, and the blowing outlet 71 t is directed downward, which can avoid cooling water. Blow out toward the center of the pressure tank 1 of the nuclear reactor 1. In this preferred embodiment, the method of removing heat from the residual heat removal system of the nuclear reactor by circulating the fuel in the furnace pressure tank will not cause the problem of fuel and stomach tremor. At this time, by restricting the carrying of the cladding to the nuclear reactor shaft ', the nuclear reactor shaft is contaminated by radiation. In addition, changing the sprayer nozzle 'can also reduce the amount of modification. Figures 11a and 11b are the nuclear reactor cooling equipment of the tenth preferred embodiment of the ninth preferred embodiment of the scope of patent application of the present invention. Figure 11a shows the fuels of Figures 1 to 7 Enlarged vertical cross-sectional view of cell 5. Figure lib is a top view of Figure 11a. In Figures 11a and lib, reference numeral 72 is a structure in the fuel pool for storing used fuel, 73 is a vertical pipe, 74 is a diffuser connected to the vertical pipe 73, and 75 is A plurality of small holes provided in the diffuser 74. In this preferred embodiment, a vertical pipe 73 in the fuel pool 5 is installed correspondingly with two upper and lower diffusers 74, and one vertical pipe 73 is provided on each side of the structure 72 in the fuel pool. There are multiple small 32 paper sizes on the diffuser 74. The Chinese standard (CNS) / V 丨 specification (21 × 297 mm) is applicable. ^ -------- ^ ------- Line I (Please read the precautions on the back before filling this page) Α7 Β7 4 6 20 6 186pif.doc / 008 V. Description of the invention (Je) The cooling water outlet 75 of the caliber is used to blow out the cooling water. The number of the diffusers 74 is not limited to four, and may be increased or decreased according to the content or the amount of cooling water. ^ The vertical pipe 73 is equivalent to the fuel pool shown in FIG. 1 of the first preferred embodiment. The circulating water injection pipe 19 of the cooling and purifying system is equivalent to the circulating water injection port 20 of the diffuser. For example, in the first preferred embodiment, a large amount of cooling water must be run into the fuel pool 5. If the diameter of the diffuser in the fuel pool 5 is not large, it may be disadvantageous to the layout in the fuel pool 5. On the other hand, from the viewpoint of cooling the fuel pool 5, it is preferable that a diffuser 74 is provided at the bottom of the fuel pool 5. At this time, the vertical pipe 73 at the bottom of the fuel pool 5 shown in FIG. 1U and FIG. On the other hand, a diffuser 74 horizontally installed at the bottom of the fuel pool is connected to a vertical pipe 73 corresponding to two upper and lower shed-like sections as shown in Fig. 11a, and the vertical pipe is shown in Fig. Ub. 73 is provided on each side of the structure 72 in the fuel pool. In this preferred embodiment, preventing the expansion of the piping caliber is really beneficial to the layout in the fuel pool 5. In the case of using a remote isolation to operate the pressure reactor channel of a nuclear reactor in a nuclear power plant, the radiation dose of the nuclear reactor well is reduced without reducing the workability, and the heat of destruction is removed. Although the diffuser 74 in FIG. 11 is described using a case where two followers are provided, three or more shed-like diffusers may be provided. In this case, the same effect as described above can be obtained. 33 (Please read the precautions on the back before filling this page) ^ -------- Order --------- Line-Qi% Discuss if this paper size applies to Chinese national standards (see CNSMO see Grid (210 X 297 mm) 4 6 20 6 3 Λ7 7186pif.doc / 008 gy ____ V. Description of the invention (M) Figure 12 illustrates the eleventh preferred implementation of item 10 of the scope of the patent application of the present invention The nuclear reactor cooling equipment in the example. In the preferred embodiment shown in FIG. 12, the A and B systems of the water supply sprayer 37 in the nuclear reactor pressure tank 1 and the nuclear reactor cooling material purification system (referred to as CCUW) are Stop valve 77, nuclear reactor cooling material purification system piping 78, stop valve 79, backflow prevention valves 80, 81, 82 and water supply system stop valve 83 are connected. 'Especially provided in the water supply system (system A) instead of the backflow prevention valve 80 The anti-backflow valve 84 with a compulsory start-up function. The anti-backflow valve 84 with a compulsory start-up function is opposite to the flow direction of the purified water to force the opening of the opposite direction corresponding to the flow direction when necessary to indicate the installation of a side pipe to prevent backflow Valve. 'Symbol 85 in Figure 12 Part of the nuclear reactor furnace grate trough is shown. Also, the nuclear reactor furnace water supply system (A system) is connected to the nuclear reactor furnace residual heat removal system (A) system pipes in a divergent manner. In the conventional example, the nuclear reactor furnace residual heat removal system ( A) The system pipeline 23 is constituted by the circulation of the first water supply spraying pipeline 46 of the water supply system 35. In the preferred embodiment, a backflow prevention valve 84 having a forced start function is provided. Here, the backflow prevention valve 84 In the forced opening state, the cooling water from the (A) system pipe 23 of the residual heat removal system of the nuclear reactor can be circulated to the first water supply spray pipe (system A) 46 and the second water supply spray pipe of the nuclear reactor furnace water supply system 35 The two sides of system B (system B) 47 circulate with each other. In the preferred embodiment, the nuclear reactor cooling material purification system piping 34. This paper size applies to Chinese national standards (CNShVi specification (210 X 297 meals) 3 ^- ------- Order --------- Line · (Please read the notes on the back before filling in this page) Jingye Wisdom Times-¾ Employee Consumption Cooperation Du printed 4 6 206 3 7186pif.doc / 008 ^ __B / V. Description of the invention (7 8 A stop valve 79 or a water supply system stop valve 83 is installed to circulate the cooling water from the cooling material purification system of the nuclear reactor to the first water supply spray line (system A) 46 or the second water supply spray line (system B) 47 ′, and the destruction heat is removed with minimal influence on the operation of the fuel exchange in the pressure tank 1 of the nuclear reactor.

又,停止閥79或給水停止閥83可以爲手動閥或電動 閥。在後者之情形下,電動閥化可改善操作性D 關於第Π圖係說明本發明之申請專利範圍第Π項之 第十二較佳實施例之核反應爐冷卻設備。 在第13圖中,與第1圖相同之部分係使用相同之符 號表示,在此省略重複部分的說明。本發明之第十二較佳 實施例與第一較佳實施例之差異點,係爲來自核反應爐殘 留熱去除系統之(B或C)系統管路24的核反應爐殘留熱 去除系統泵25的吸入口上游側分歧之核反應爐冷卻材料 淨化系統管路78於串連連接核反應爐冷卻材料淨化系統 再生熱交換器86、核反應爐冷卻材料淨化系統非再生熱交 換器87、核反應爐冷卻材料淨化系統泵88及核反應爐冷 卻材料淨化系統過濾除氯裝置89與核反應爐冷卻材料淨 化系統後,連接接於核反應爐給水系統35上之核反應爐 冷卻材料淨化系統循環管路93。 又,核反應爐冷卻材料淨化系統再生熱交換器86經 由停止閥90與核反應爐冷卻材料淨化系統循環管路93相 連接,在核反應爐冷卻材料淨化系統過濾除氯裝置89之 出口側分歧處與核反應爐冷卻材料淨化系統循環管路9 3 35 本紙張尺度適用中國國家標準(CNSVV1規格(210 X 297公釐) -------^---I--I I --— In--^ I {請先閱讀背面之注意事項再填寫本頁) 462063 Λ7 _Ii8-6pi£-d〇C/〇°8__B7__ 五、發明說明U5!) 之間連接有核反應爐冷卻材料淨化系統側管管略91,且在 核反應爐冷卻材料淨化系統側管管路91上設有側管閥 92。 在本較佳實施例中,核反應爐冷卻材料淨化系統再生 熱交換器86運轉經由側管,以在核能發電廠中,利用遠 隔離操作核反應爐壓力槽1通路之情形下,以不降低作業 性,並抑制核反應爐井之放射線以降低放射劑量,以高效 率地進行破壞熱之去除。 關於第13圖係說明本發明之申請專利範圍第12項之 第一較佳實施例之核反應爐冷卻設備的運轉方法。 在上述本發明之申請專利範圍第1項係爲第一較佳實 施例之核反應爐冷卻設備。由第1圖所示,在燃料池冷卻 淨化系統過濾除氯裝置11的側管閥14係爲關閉之情形 下,在本較佳實施例中,具有如第13圖所示之開啓側管 閥14之狀態進行運轉的特徵。開啓側管閥14時,燃料池 冷卻淨化系統泵開始吐出燃料池水流至燃料池冷卻淨化系 統過濾除氯裝置11與燃料池冷卻淨化系統側管管路15中 再匯流至燃料池冷卻淨化系統熱交換器13中時流入之流 量增加。 接著,利用燃料池冷卻淨化系統熱交換器13冷卻之 冷卻水由燃料池循環管路17經由核反應爐殘留熱去除系 統循環水注入管路31而流入核反應爐井4內,再流入核 反應爐壓力槽1內。 在本較佳實施例中,在燃料池冷卻淨化系統過濾除氯 36 本紙張尺度適用中國國家標準(CNS)/\J規格(210 X 297公釐) . ----^'-------訂 ------線 (請先閱讀背面之注意事項再填寫本頁) 462063The stop valve 79 or the feed water stop valve 83 may be a manual valve or an electric valve. In the latter case, the electric valve can improve the operability D. About FIG. Π illustrates the nuclear reactor cooling equipment of the twelfth preferred embodiment of item Π of the present invention. In FIG. 13, the same parts as those in FIG. 1 are denoted by the same symbols, and the description of the duplicated parts is omitted here. The difference between the twelfth preferred embodiment of the present invention and the first preferred embodiment is that of the nuclear reactor furnace residual heat removal system pump 25 from the (B or C) system pipe 24 of the nuclear reactor residual heat removal system. The nuclear reactor cooling material purification system pipe 78 diverging upstream of the suction port is connected in series to the nuclear reactor cooling material purification system regeneration heat exchanger 86, the nuclear reactor cooling material purification system non-regenerative heat exchanger 87, and the nuclear reactor cooling material purification system. The pump 88 and the nuclear reactor cooling material purification system filtering and dechlorinating device 89 and the nuclear reactor cooling material purification system are connected to the nuclear reactor cooling material purification system circulation pipeline 93 connected to the nuclear reactor furnace water supply system 35. In addition, the regenerative heat exchanger 86 of the cooling material purification system of the nuclear reactor is connected to the circulation line 93 of the cooling material purification system of the nuclear reactor through a stop valve 90, and the nuclear reaction is performed at a branch of the nuclear reactor cooling material purification system at the exit side of the chlorine removal device 89 Furnace cooling material purification system circulation pipe 9 3 35 This paper size applies to Chinese national standard (CNSVV1 specification (210 X 297 mm) ------- ^ --- I--II --- In-^ I (Please read the precautions on the back before filling this page) 462063 Λ7 _Ii8-6pi £ -d〇C / 〇 ° 8__B7__ V. Description of the invention U5!) A nuclear reactor cooling material purification system side pipe tube is connected between 91 A side pipe valve 92 is provided on the side pipe line 91 of the cooling material purification system of the nuclear reactor. In the present preferred embodiment, the regeneration heat exchanger 86 of the cooling material purification system of the nuclear reactor is operated via a side pipe, so that in a nuclear power plant, a remote isolation operation of the pressure tank 1 channel of the nuclear reactor is performed so as not to reduce workability. And suppress the radiation of the nuclear reactor well to reduce the radiation dose, and efficiently remove the destruction heat. Fig. 13 illustrates the operation method of the nuclear reactor cooling equipment of the first preferred embodiment of item 12 of the scope of patent application of the present invention. The first item in the above patent application scope of the present invention is the nuclear reactor cooling equipment of the first preferred embodiment. As shown in FIG. 1, in a case where the side pipe valve 14 of the filtering and dechlorinating device 11 of the fuel pool cooling and purifying system is closed, in the preferred embodiment, the side pipe valve is opened as shown in FIG. 13. 14 state running characteristics. When the side pipe valve 14 is opened, the fuel pool cooling and purification system pump starts to discharge the fuel pool water to the fuel pool cooling and purification system filtering and dechlorinating device 11 and the fuel pool cooling and purification system side pipe line 15 and then merges to the fuel pool cooling and purification system heat. When the exchanger 13 is in flow, the flow rate increases. Next, the cooling water cooled by the heat exchanger 13 of the fuel pool cooling and purification system flows from the fuel pool circulation pipe 17 through the nuclear reactor residual heat removal system circulating water injection pipe 31 into the nuclear reactor well 4 and then into the nuclear reactor pressure tank. 1 within. In the preferred embodiment, the chlorine is filtered and removed in the fuel pool cooling and purification system. The paper size is applicable to the Chinese National Standard (CNS) / \ J specification (210 X 297 mm). ---- ^ '---- --- Order ------ line (please read the precautions on the back before filling this page) 462063

AT 7186pif·doc/008 五、發明說明) 裝置Η的側管閥14開啓狀態下運轉,則燃料池冷卻淨化 系統的系統流量會增大,同時增大燃料池冷卻淨化系統熱 交換器13之流量,而提高燃料池冷卻淨化系統管路之除 熱效率。因此,可以在核能發電廠中,利用遠隔離操作核 反應爐壓力槽1通路之情形下,以不降低作業性,並抑制 核反應爐井之放射線以降低放射劑量,以去除破壞熱。 第14圖係說明本發明之申請專利範圍第13項之第二 較佳實施例之核反應爐冷卻設備的運轉方法。 在第14圖中,與第1圖相同之部分係使用相同之符 號表示,在此省略重複部分的說明。在第14圖中,核反 應爐殘留熱去除系統之(Α)系統管路23稱爲第一系統, 核反應爐殘留熱去除系統管路24之Β系統稱爲第二系統, 同樣的C系統則稱爲第三系統。 在本較佳實施例中,利用第一系統冷卻之冷卻水循環 至核反應爐給水系統35中,利用第二系統冷卻之冷卻水 由核反應爐殘留熱去除系統-燃料池冷卻淨化系統連接管 路經由燃料池冷卻淨化系統循環水注入管路19循環至燃 料池5中,在第一系統中,自燃料池水中取水,利用核反 應爐殘留熱去除系統熱交換器26冷卻後,進行運轉循環 至前述燃料池5中。又,燃料池冷卻淨化系統管路8係自 燃料池水中取水,利用燃料池冷卻淨化系統過濾除氯裝置 Η淨化之後,由抑制池淨化系統管路16循環至核反應爐 井4或設於鄰接核反應爐井4之機器預置池中(未圖示)° 本較佳實施例係爲利用核反應爐殘留熱去除系統熱交 37 本紙張尺度適用t國國家標準(CNS)A..l規格(210 X 297公釐) (請先閱讀背面之注意事項再填寫本頁) 訂· 線_ 4 62〇6 3 B7 7 1 8 6pl f * cioc / 0 0 8 五、發明說明(4() 換器26去除破壞熱,與利用燃料池冷卻淨化系統之淨化 功能之運轉方法。因此,利用核反應爐殘留熱去除系統之 3系統的冷卻運轉,可完全具有規格之運轉50%程度之系 統流量的除熱能力。因此可在循環至燃料池5及核反應爐 給水系統35之過程中降低受核反應爐井4之感染之放射 線劑量。 又,燃料池冷卻淨化系統之淨化運轉係自燃料池冷卻 淨化系統過濾除氯裝置11流出,再經由抑制池淨化系統 管路16循環至核反應爐井4或機器預置池中。如此,可 以在核能發電廠中,利用遠隔離操作核反應爐壓力槽1通 路之情形下,以不降低作業性,並抑制核反應爐井之放射 線以降低放射劑量,以去除破壞熱。 第15圖係說明本發明之申請專利範圍第14項之第三 較佳實施例之核反應爐冷卻設備的運轉方法。 在第15圖中,與第1圖相同之部分係使用相同之符 號表示,在此省略重複部分的說明。在第15圖中,核反 應爐殘留熱去除系統之(A)系統管路23及核反應爐殘留 熱去除系統之(B或C)系統管路24之各自的核反應爐殘 留熱去除系統熱交換器26之出口側與進口側與連接有停 止閥95之連接管路94串連連接。在核反應爐殘留熱去除 系統泵25的吐出側與核反應爐殘留熱去除系統防止逆流 閥96相連接,核反應爐殘留熱去除系統熱交換器26之出 口側與核反應爐殘留熱去除系統管路上之熱交換器出口側 停止閥97相連接。 38 I------!k---I----訂·--------線 (請先間讀背面之注意事項再填寫本頁) 齊 % 本紙張尺度適用中國國家標準(CNS)A4規格(210x297公坌> i ^62063 718epif.d〇c/00S_^___ 五、發明說明(以) 核反應爐殘留熱去除系統防止逆流閥96之出口側與 熱交換器出口側停止閥97的出口側之間分岐連接核反應 爐殘留熱去除系統熱交換器側管管路98,此側管管路98 上安裝有側管閥99。核反應爐殘留熱去除系統熱交換器連 接管路94之停止閥95、95之間分歧連接放射性廢棄物處 理系統連接管路100,放射性廢棄物處理系統連接管路100 經由停止閥101與放射性廢棄物處理設備102相連接。 在本較佳實施例中,核反應爐殘留熱去除系統之(A) 系統管路23與核反應爐殘留熱去除系統之(B或C)系統 管路24的核反應爐殘留熱去除系統熱交換器26與放射性 廢棄物處理系統連接管路1〇〇及核反應爐殘留熱去除系統 熱交換器側管管路98的系統連接,利用多個核反應爐殘 留熱去除系統熱交換器26串連連接之運轉,以提高破壞 熱去除效率,並可在不降低作業性之情形下,降低放射線 感染劑量。 又,雖然在第Π圖中係以核反應爐殘留熱去除系統 之冷卻水循環至燃料池5爲例進行記載,然也可以進行由 低壓注水系統噴霧器36或給水噴霧器37循環至核反應爐 壓力槽1中的運轉。 在本發明之中係可以在核能發電廠中,利用遠隔離操 作核反應爐壓力槽通路之情形下,以不降低作業性,並抑 制核反應爐井之放射線以降低放射劑量,以去除破壞熱。 雖然本發明已以一較佳實施例揭露如上,然其並非用 以限定本發明,任何熟習此技藝者,在不脫離本發明之精 3S.--------訂---------線. (請先閲讀背面之注意事項再填寫本頁) 本紙張尺度適用中國國家標準(CNSM.丨規格(2]〇 X 297公釐> Λ62063 Λ7AT 7186pif · doc / 008 V. Description of the invention) When the side pipe valve 14 of the device 运转 is opened, the system flow of the fuel pool cooling and purification system will increase, and the flow rate of the heat exchanger 13 of the fuel pool cooling and purification system will increase. , And improve the heat removal efficiency of the fuel pool cooling and purification system. Therefore, in a nuclear power plant, remote isolation operation of the reactor pressure tank 1 channel can be used without reducing workability and suppressing radiation from the nuclear reactor well to reduce radiation dose to remove heat of destruction. Fig. 14 illustrates the operation method of the nuclear reactor cooling equipment of the second preferred embodiment of the thirteenth patent application scope of the present invention. In Fig. 14, parts that are the same as those in Fig. 1 are denoted by the same symbols, and repeated descriptions are omitted here. In FIG. 14, the (A) system pipe 23 of the residual heat removal system of the nuclear reactor is referred to as the first system, the B system of the pipe 24 of the residual heat removal system of the nuclear reactor is referred to as the second system, and the same C system is referred to as For the third system. In the preferred embodiment, the cooling water cooled by the first system is circulated to the water supply system 35 of the nuclear reactor, and the cooling water cooled by the second system is passed by the nuclear reactor residual heat removal system-fuel pool cooling and purification system connection pipeline via the fuel. The circulating cooling water injection pipe 19 of the pool cooling and purification system is circulated to the fuel pool 5. In the first system, water is taken from the fuel pool water, cooled by the heat exchanger 26 of the residual heat removal system of the nuclear reactor, and the operation cycle is performed to the aforementioned fuel pool. 5 in. In addition, the fuel pool cooling and purifying system pipeline 8 draws water from the fuel pool water, and the fuel pool cooling and purifying system is used to filter the chlorine removal device. After purification, the fuel pool cooling and purification system pipeline 16 is circulated to the nuclear reactor well 4 or located adjacent to the nuclear reaction. In the machine presetting pool of furnace shaft 4 (not shown) ° This preferred embodiment uses the residual heat removal system of a nuclear reactor to heat the paper. 37 This paper size is applicable to national standards (CNS) A..l specifications (210 X 297 mm) (Please read the precautions on the back before filling this page) Order · Thread_ 4 62〇6 3 B7 7 1 8 6pl f * cioc / 0 0 8 V. Description of the invention (4 () Converter 26 The operation method of removing the destruction heat and using the purification function of the fuel pool cooling and purification system. Therefore, the cooling operation of the 3 system using the residual heat removal system of the nuclear reactor can completely have the heat removal ability of the system flow of about 50% of the specification. Therefore, it is possible to reduce the radiation dose infected by the nuclear reactor well 4 during the cycle to the fuel pool 5 and the nuclear reactor furnace water supply system 35. Moreover, the purification operation of the fuel pool cooling purification system is from the fuel pool cooling purification system The system filters out the chlorine removal device 11 and circulates it to the nuclear reactor well 4 or the machine preset pool through the suppression pool purification system pipeline 16. In this way, in a nuclear power plant, remote isolation operation of the nuclear reactor pressure tank 1 can be used. In this case, in order not to reduce the workability, and to suppress the radiation of the nuclear reactor well to reduce the radiation dose to remove the destruction heat. Figure 15 illustrates the nuclear reactor of the third preferred embodiment of the 14th scope of the patent application of the present invention. The operation method of the cooling equipment. In FIG. 15, the same parts as those in FIG. 1 are denoted by the same symbols, and repeated descriptions are omitted here. In FIG. 15, (A) of the residual heat removal system of the nuclear reactor System pipe 23 and (B or C) system residual heat removal system (B or C) system pipe 24 The respective nuclear reactor residual heat removal system heat exchanger 26 is connected to the outlet and inlet sides of the heat exchanger 26 with a stop valve 95 94 is connected in series. The discharge side of the pump 25 of the nuclear reactor residual heat removal system is connected to the nuclear reactor residual heat removal system prevention counterflow valve 96, and the nuclear reactor residual heat removal system The outlet side of the exchanger 26 is connected to the heat exchanger outlet side stop valve 97 on the pipe of the residual heat removal system of the nuclear reactor. 38 I ------! K --- I ---- Order · --- ----- Line (please read the precautions on the back before filling this page) Qi% This paper size is applicable to China National Standard (CNS) A4 (210x297 cm) i ^ 62063 718epif.d〇c / 00S_ ^ ___ 5. Description of the invention (to) The nuclear reactor furnace residual heat removal system prevents the divergence between the outlet side of the counter-flow valve 96 and the heat exchanger outlet side stop valve 97 to connect the nuclear reactor furnace residual heat removal system heat exchanger side tube Circuit 98, a side pipe valve 99 is installed on this side pipe line 98. Nuclear reactor furnace residual heat removal system heat exchanger connection line 94, stop valve 95, 95 are connected to the radioactive waste treatment system connection line 100, and the radioactive waste treatment system connection line 100 is connected to the radioactive waste through the stop valve 101 The processing equipment 102 is connected. In the preferred embodiment, (A) system piping 23 of the nuclear reactor residual heat removal system and (B or C) system piping 24 of the nuclear reactor residual heat removal system heat exchanger 26 of the nuclear reactor residual heat removal system The system is connected to the radioactive waste treatment system connection line 100 and the nuclear reactor residual heat removal system heat exchanger side pipe line 98. It uses a plurality of nuclear reactor residual heat removal system heat exchangers 26 to operate in series. In order to improve the destruction heat removal efficiency, and reduce the radiation infection dose without reducing the workability. In addition, although the cooling water of the nuclear reactor furnace residual heat removal system is circulated to the fuel pool 5 as an example in the figure Π, it is also possible to circulate the low pressure water injection system sprayer 36 or the water supply sprayer 37 to the nuclear reactor pressure tank 1 Operation. In the present invention, in a nuclear power plant, a remote isolation operation of the pressure tank path of a nuclear reactor can be used without reducing workability, and by suppressing radiation from a nuclear reactor well to reduce radiation dose to remove heat of destruction. Although the present invention has been disclosed as above with a preferred embodiment, it is not intended to limit the present invention. Anyone skilled in this art will not depart from the essence of the present invention. 3 ----- Line. (Please read the precautions on the back before filling this page) This paper size applies to Chinese National Standards (CNSM. 丨 Specifications (2) 〇X 297mm > Λ62063 Λ7

7 1 8 6pi f . doc / 0 0 S 五、發明說明) 神和範圍內,當可作各種之更動與潤飾。 本紙張尺度適用中國國家標準(CNS)A丨規恪UlOx 297公坌) ----------I! -^i —---II 訂--I----I* 線 (請先閱讀背面之注意事項再填寫本頁)7 1 8 6pi f. Doc / 0 0 S V. Description of the invention) Within the scope of God and God, various changes and modifications can be made. This paper size applies to China National Standard (CNS) A 丨 Ulx Ul297 坌) ---------- I!-^ I ----- II Order --I ---- I * line (Please read the notes on the back before filling this page)

Claims (1)

0^88^ ABCS d 6 2 0 6 ^ 718 6pi f ‘ doc/Ο 〇 8 六、申請專利範圍 1· 一種核反應爐冷卻設備’係具備有在一核反應爐井 及一燃料池之間構築一池閥;在該核反應爐并及該燃料池 之中,至少連接有一水源與一具有過濃除氯裝置之燃料池 冷卻淨化系統管路;在該核反應爐井的底部垂直設有一核 反應爐壓力槽;連接於該核反應爐壓力槽之一熱交換器, 該熱交換器具備有複數個系統之一核反應爐殘留熱去除系 統管路;其特徵爲: 連接於該燃料池冷卻淨化系統管路之下游側之一燃料 池循環管路之循環水注入口設置於該核反應爐井內;以及 該核反應爐殘留熱去除系統管路之下游側循環管路之 循環水注入口設置於該燃料池內。 2. —種核反應爐冷卻設備,係具備有在一核反應爐井 及一燃料池之間構築一池閥;在該核反應爐井及該燃料池 之中,至少連接有一水源與一具有過濾除氯裝置之燃料池 冷卻淨化系統管路;在該核反應爐井的底部垂直設有一核 反應爐壓力槽;連接於該核反應爐壓力槽之一熱交換器, 該熱交換器具備有複數個系統之一核反應爐殘留熱去除系 統管路;其特徵爲: 連接於該燃料池冷卻淨化系統管路之下游側之一燃料 池循環管路之循環水注入口設置於該核反應爐井內; 該核反應爐殘留熱去除系統管路之下游側循環管路之 循環水注入口設置於該燃料池內;以及 該燃料池冷卻淨化系統管路之一冷卻水循環至該燃料 池或該核反應爐井,或在該核反應爐殘留熱去除系統管路 一^^@家標準(CNS)A4規格⑵ϋ X 297公坌) — — — — — — —— — — — I.^·1—1ιι1— ·11·ι·ιι_ — (請先閲讀背面之注意事項再填寫本頁) 經濟部智慧財產局員工消費合作社印製 2 3 WBCD 經濟部智慧財產局員工消費合作杜印製 六、申請專利範圍 之該冷卻水循環至該核反應爐井或該燃料池之前,設置有 一切換操作管路。 3. 如申請專利範圍第1項或第2項所述之核反應爐冷 卻設備,其中該些系統之該核反應爐殘留熱去除系統管路 之中,至少有一個系統連接設置於該核反應爐壓力槽內的 一給器,或分歧連接設置於該核反應爐壓力槽內的 一低統噴霧器。 4. 始範圍第 1項所述之核反應爐冷卻設備’ 其中在該環管路與該燃料池冷卻淨化循環水注入 管路之間,連接有一防止逆流閥與一停止閥’且在該核反 應爐殘留熱去除系統中設置有一熱交換器’該熱交換器冷 卻連接於該燃料池冷卻淨化系統循環水注入管路與該核反 應爐給水系統管路的一冷卻水出口側管路。 5. —種核反應爐冷卻設備,係具備有在一核反應爐井 及一燃料池之間構築一池閥;在該核反應爐井的底部垂直 設有一核反應爐壓力槽;連接於該核反應爐壓力槽之一核 反應爐殘留熱去除系統管路;其特徵爲: 該核反應爐殘留熱去除系統管路之下游側循環管路之 一循環水注入口設置於該核反應爐井內;以及 由該核反應爐殘留熱去除系統管路至該核反應爐井之 上部之間分歧連接有一核反應爐井取水管路。 6. —種核反應爐冷卻設備,係具備有在一核反應爐井 及一燃料池之間構築一池閥;在該核反應爐井及該燃料池 之中,至少連接有一水源與一具有第一過濾除氯裝置之燃 42 本紙張尺度過用中國國家標準(CNS)A4規格(2]〇 X 297公g ) (請先閱讀背面之注意事項再填寫本頁) ϋ t— a^i · t 1» n n I n I 線- d 6 20 63 7196pif , doc/ A8 Βδ 00 8 D8 經濟部智慧財產局員工消費合作社印®^ 六、申請專利範圍 料'池冷卻淨化系統管路;在該核反應爐井的底部垂直設有 一核反應爐壓力槽;連接於該核反應爐壓力槽之一熱交換 器’該熱交換器具備有複數個系統之一核反應爐殘留熱去 除系統管路;其特徵爲: 在該核反應爐殘留熱去除系統管路之一冷卻水出口側 配管系統中設置有一過濾器或一第二過濾除氯裝置。 7·如申請專利範圍第1項或第2項所述之核反應爐冷 卻設備’其中該些循環管路之一至少連接一個設置在該核 反應爐井內之一核反應爐井噴霧器,該核反應爐井噴霧器 之一冷卻水吹出口,各自設成朝向該核反應爐壓力槽之一 中心線之斜下方向與朝向該中心線之水平方向。 8_如申請專利範圍第1項或第2項所述之核反應爐冷 卻設備’其中在該核反應爐壓力槽內設置有一低壓注水系 統噴霧器’且該低壓注水系統噴霧器之吹出水之流動方向 設定爲向下。 9. 如申請專利範圍第1項或第2項所述之核反應爐冷 卻設備,其中在該燃料池內之複數個冷卻水吹出孔上設置 有複數個棚段狀擴散器。 10. 如申請專利範圍第1項或第2項所述之核反應爐 冷卻設備,其巾在_麵軸雜有2藏的複數個給 水噴霧器,以連接一第一給水管路與一第二給水管路,在 該些給水管路與-核反應爐冷卻材料淨化系統管路之, 接有-第-防止逆流閥H防止逆流閥,該核反應爐 冷卻材料淨化系統管路,係包括該第一給水管路與該第— 43 ------------^.!-----訂 i I n n I 線· <請先閱讀背面之注意事項再填寫本頁) 本紙張尺度適用中闯國家標举(CNS)A4規格(210 x 297公f ) A8B8C8D8 經濟部智慧財產局員工消費合作社印?¾¾ 六、申請專利範圍 防止逆流閥之間連接有該核反應爐殘留熱去除系統管路, 且該第一防止逆流閥係爲具強制開機功能之防止逆流閥。 11. 一種核反應爐冷卻設備’其具備有在一核反應爐 井及一燃料池之間構築一池閥;在該核反應爐井及該燃料 池之中,至少連接有一水源與一具有過濾除氯裝置之燃料 池冷卻淨化系統管路;在該核反應爐井的底部垂直設有一 核反應爐壓力槽;連接於該核反應爐壓力槽之一熱交換 器,該熱交換器具備有一核反應爐殘留熱去除系統管路; 其特徵爲: 由該核反應爐殘留熱去除系統管路分岐連接一再生熱 交換器及設有具過濾除氯裝置之一核反應爐冷卻材料淨化 系統管路; 該核反應爐冷卻材料淨化系統管路的'過濾除氯·裝置之 出口側連接有連接於該核反應爐給水系統管路之一核反應 爐冷卻材料淨化系統循環管路;以及 在該核反應爐冷卻材料淨化系統循環管路上設有具有 側管熱交換器之一核反應爐冷卻材料淨化系統側管管路。 12. —種核反應爐冷卻設備之運轉方法’係具備有在 一核反應爐井及一燃料池之間構築一池閥;在該核反應爐 井及該燃料池之中,至少連接有一水源、一過濾除氯裝置 及具有熱交換器之一燃料池冷卻淨化系統管路;在該核反 應爐井的底部垂直設有一核反應爐壓力槽;該核反應爐壓 力槽經由一停止閥連接一具備依序連接有一核反應爐殘留 熱去除系統管路之一熱交換器’其特徵爲: 44 Ϊ紙張尺度適Ρ國國家样'準(CNS)A4規格(2]0 X 297公釐) (請先閲讀背面之注意事項再填寫本頁) ,4------- 訂-----. 462063 7186pif .doc/008 A8 B8 C8 D8 經濟部智慧財產局員工消費合作社印*11^ 六、申請專利範圍 該燃料池冷卻淨化系統管路的過濾除氯裝置中設有具 一側管閥之一側管管路;以及 該側管管路之該側管閥爲開啓狀態時,流向該燃料池 冷卻淨化系統管路之熱交換器的流量會增加。 13. —種核反應爐冷卻設備之運轉方法,係具備有在 —核反應爐井及一燃料池之間構築一池閥;在該核反應爐 井及該燃料池之中,至少連接有一水源與具有過濾除氯裝 置之一燃料池冷卻淨化系統管路;在該核反應爐井的底部 垂直設有一核反應爐壓力槽;連接於該核反應爐壓力槽之 具備有複數個系統之一核反應爐殘留熱去除系統管路之一 熱交換器;連接該核反應爐殘留熱去除系統管路與該燃料 池冷卻淨化系統管路之一核反應爐殘留熱去除系統-燃料 池冷卻淨化系統連接管路,其特徵爲: 具有該些系統之該核反應爐殘留熱去除系統係具有一 第一系統、一第二系統與一第三系統之三系統,其中該第 一系統係利用該第一系統之熱交換器冷卻該核反應爐給水 系統或循環至該燃料池的冷卻水、該第二系統係利用該第 二系統之熱交換器冷卻循環至該燃料池的冷卻水、該第三 系統也是利用該第三系統之熱交換器冷卻循環至該燃料池 的冷卻水;以及 該燃料池冷卻淨化系統管路係由該燃料池中取水,淨 化之後’經由一抑制池淨化系統循環至該核反應爐井或一 機器預置池。 14· 一種核反應爐冷卻設備之運轉方法,係具備有在 45 本紙張义度適用中國國家標準(CNS)A4規格(2]0 X 297公筻) ------------- ill — — — — ·!1111!11 . (請先閱讀背面之注意事項再填寫本頁) 8 ο ο / C 0 d f i p 386 671 ο 2 6 8888 ABCD 六、申請專利範圍 一核反應爐井及一燃料池之間構築一池閥;在該核反應爐 井及該燃料池之中,至少連接有一水源與具有過濾除氯裝 置之一燃料池冷卻淨化系統管路;在該核反應爐井的底部 垂直設有一核反應爐壓力槽;連接於該核反應爐壓力槽之 具有一核反應爐殘留熱去除系統管路之熱交換器,其特徵 爲: 該核反應爐殘留熱去除系統係具有一第一系統至一第 三系統之三系統、在該第一系統至該第三系統中,係各自 設有至少2個串連連接運轉的熱交換器。 ------------ 衣-----!t訂---------線 (請先閱讀背面之注意事項再填寫本頁) 經濟部智慧財產局員工消費合作社印制^ 46 本紙張尺度適用中國國家標準(CNS)A4規格(2]0 X 297公g )0 ^ 88 ^ ABCS d 6 2 0 6 ^ 718 6pi f 'doc / 〇 〇 8 6. Scope of patent application 1. A nuclear reactor cooling equipment' is equipped with a tank valve constructed between a nuclear reactor shaft and a fuel pool ; At least one water source is connected to the nuclear reactor and the fuel pool with a fuel pool cooling and purifying system pipeline having an over-concentration chlorine removal device; a nuclear reactor pressure tank is vertically arranged at the bottom of the nuclear reactor shaft; connected to A heat exchanger of the pressure tank of the nuclear reactor, the heat exchanger having one of a plurality of systems, a residual heat removal system pipe of the nuclear reactor, and characterized in that it is connected to one of the downstream sides of the fuel pool cooling and purification system pipe A circulating water injection port of a fuel tank circulation pipeline is disposed in the nuclear reactor well; and a circulating water injection port of a downstream side circulation pipeline of the nuclear reactor furnace residual heat removal system pipeline is disposed in the fuel pool. 2. —A kind of nuclear reactor furnace cooling equipment, which is provided with a pool valve constructed between a nuclear reactor furnace and a fuel pool; at least one water source is connected to the nuclear reactor furnace and the fuel pool with a filter and chlorine removal device Fuel tank cooling and purification system pipeline; a nuclear reactor pressure tank is vertically arranged at the bottom of the nuclear reactor furnace; a heat exchanger connected to the nuclear reactor pressure tank, the heat exchanger is provided with a nuclear reactor furnace residue of a plurality of systems The heat removal system pipeline is characterized in that: a circulating water injection port of a fuel pool circulation pipeline connected to a downstream side of the fuel pool cooling and purification system pipeline is disposed in the nuclear reactor well; the nuclear reactor residual heat removal system The circulating water injection port of the circulation pipe on the downstream side of the pipeline is arranged in the fuel pool; and one of the cooling pool purification system pipes' cooling water is circulated to the fuel pool or the nuclear reactor well, or the residual heat in the nuclear reactor Remove the system piping a ^^ @ 家 标准 (CNS) A4 size (X 297 male)) — — — — — — — — — — I. ^ · 1—1ιι1 — · 11 · ι · ιι_ — (Please read the notes on the back before filling this page) Printed by the Consumers ’Cooperative of Intellectual Property Bureau of the Ministry of Economic Affairs 2 3 WBCD Printed by the Consumer ’s Cooperative of Intellectual Property Bureau of the Ministry of Economic Affairs Before the cooling water is circulated to the nuclear reactor shaft or the fuel pool, a switching operation pipeline is provided. 3. The nuclear reactor cooling equipment according to item 1 or 2 of the scope of the patent application, wherein at least one system connection of the nuclear reactor furnace residual heat removal system pipelines of these systems is arranged in the nuclear reactor furnace pressure tank An internal feeder, or a low-level sprayer arranged in the pressure tank of the nuclear reactor in a bifurcated manner. 4. The nuclear reactor cooling equipment described in item 1 of the initial range, wherein a loop prevention valve and a stop valve are connected between the ring pipeline and the fuel pool cooling and purification circulating water injection pipeline, and the nuclear reactor is A heat exchanger is provided in the residual heat removal system, and the heat exchanger cools a cooling water outlet-side pipe connected to the circulating water injection pipe of the fuel pool cooling and purification system and the water supply system pipe of the nuclear reactor. 5. —A kind of nuclear reactor cooling equipment, which is equipped with a tank valve constructed between a nuclear reactor shaft and a fuel pool; a nuclear reactor pressure tank is vertically arranged at the bottom of the nuclear reactor shaft; connected to the nuclear reactor pressure tank A nuclear reaction furnace residual heat removal system pipeline; characterized in that: a circulating water injection port of a downstream side circulation pipeline of the nuclear reaction furnace residual heat removal system pipeline is arranged in the nuclear reaction furnace well; and the nuclear reaction furnace residual heat A nuclear reaction furnace water intake pipeline is connected from the removal system pipeline to the upper part of the nuclear reaction furnace shaft. 6. —A kind of nuclear reactor furnace cooling equipment, which is provided with a pool valve constructed between a nuclear reactor furnace and a fuel pool; at least one water source is connected between the nuclear reactor furnace and the fuel pool, and a first filter for removing chlorine Burning of the device 42 This paper has been oversized in Chinese National Standard (CNS) A4 (2) 〇X 297g (Please read the precautions on the back before filling this page) ϋ t— a ^ i · t 1 »nn I n I line-d 6 20 63 7196pif, doc / A8 Βδ 00 8 D8 Printed by the Consumer Cooperative of the Intellectual Property Bureau of the Ministry of Economic Affairs ^ 六 、 Patent application scope Material cooling pool purification system pipeline; at the bottom of the nuclear reactor well A nuclear reactor pressure tank is provided vertically; a heat exchanger connected to the nuclear reactor pressure tank is provided. The heat exchanger is provided with one of a plurality of systems, and the residual heat removal system piping of the nuclear reactor is characterized by: A filter or a second filtering and dechlorinating device is arranged in the cooling water outlet side piping system of one of the pipes of the heat removal system. 7. The nuclear reactor furnace cooling equipment as described in the scope of application for item 1 or item 2, wherein one of the circulation pipelines is connected to at least one nuclear reactor furnace sprayer arranged in the nuclear reactor furnace, the nuclear reactor furnace One of the cooling water blowing outlets of the atomizer is respectively set to the oblique downward direction toward a center line of the pressure tank of the nuclear reactor and the horizontal direction toward the center line. 8_ The nuclear reactor cooling equipment described in item 1 or 2 of the scope of the patent application 'wherein a low pressure water injection system sprayer is set in the pressure tank of the nuclear reactor' and the flow direction of the blown water of the low pressure water injection system sprayer is set to down. 9. The cooling device for a nuclear reactor as described in item 1 or 2 of the scope of the patent application, wherein a plurality of shed-like diffusers are provided on the plurality of cooling water blowing holes in the fuel pool. 10. The nuclear reactor furnace cooling equipment as described in the first or second scope of the patent application, the towel is mixed with a plurality of water supply sprayers hidden in the surface axis to connect a first water supply line and a second water supply The pipeline, between the water supply pipeline and the nuclear reaction furnace cooling material purification system pipeline, is connected to a -th-reverse flow prevention valve H prevention reverse flow valve, the nuclear reaction furnace cooling material purification system pipeline includes the first feed water Piping and the first — 43 ------------ ^.! ----- Order i I nn I line < Please read the notes on the back before filling this page) This paper The standard applies to the CNS A4 specification (210 x 297 male f) A8B8C8D8 printed by the employee consumer cooperative of the Intellectual Property Bureau of the Ministry of Economic Affairs? ¾¾ 6. Scope of patent application The pipelines of the residual heat removal system of the nuclear reactor are connected between the anti-reverse valves, and the first anti-reverse valve is an anti-reverse valve with a forced start function. 11. A nuclear reactor furnace cooling device, which is provided with a pool valve constructed between a nuclear reactor furnace and a fuel pool; at least one water source and a fuel having a filtering and dechlorinating device are connected between the nuclear reactor furnace and the fuel pool. The cooling and purification system pipeline of the pool; a nuclear reactor pressure tank is vertically arranged at the bottom of the nuclear reactor furnace shaft; a heat exchanger connected to the nuclear reactor furnace pressure tank, the heat exchanger is provided with a nuclear reactor furnace residual heat removal system pipeline; It is characterized in that the pipe of the residual heat removal system of the nuclear reactor is divided into a regenerative heat exchanger and a pipe of a nuclear reactor cooling material purification system provided with a filter and chlorine removal device; 'The outlet side of the filtering and dechlorination device is connected with a nuclear reaction furnace cooling material purification system circulation pipeline connected to one of the nuclear reaction furnace water supply system pipelines; and the nuclear reaction furnace cooling material purification system circulation pipeline is provided with a side pipe heat One of the exchangers is the side pipe of the cooling material purification system of the nuclear reactor. 12. —A method of operating a nuclear reactor cooling equipment 'is provided with a pool valve constructed between a nuclear reactor shaft and a fuel pool; at least one water source is connected to the nuclear reactor shaft and the fuel pool, and a filter is used to remove chlorine The device and a fuel pool cooling and purification system pipeline having a heat exchanger; a nuclear reactor pressure tank is vertically arranged at the bottom of the nuclear reactor furnace shaft; the nuclear reactor furnace pressure tank is connected via a stop valve with a nuclear reactor furnace residue connected in sequence One of the heat removal system pipes' heat exchanger 'is characterized by: 44 Ϊ Paper size is suitable for national and national standards' (CNS) A4 specification (2) 0 X 297 mm) (Please read the precautions on the back before filling (This page), 4 ------ Order -----. 462063 7186pif .doc / 008 A8 B8 C8 D8 Printed by the Consumer Cooperatives of the Intellectual Property Bureau of the Ministry of Economic Affairs * 11 ^ VI. Application scope of the patent The fuel pool cooling The filtering and dechlorinating device of the purification system pipeline is provided with a side pipe pipeline having a side pipe valve; and when the side pipe valve of the side pipe pipeline is open, it flows to the fuel pool cooling and purification system pipeline. Heat exchanger flow The amount will increase. 13. —A method for operating cooling equipment of a nuclear reactor, which is provided with a pool valve constructed between a nuclear reactor furnace and a fuel pool; at least one water source is connected between the nuclear reactor furnace and the fuel pool and a filter is used to remove chlorine One of the devices is a fuel pool cooling and purification system pipeline; a nuclear reactor pressure tank is vertically arranged at the bottom of the nuclear reactor furnace shaft; and a nuclear reactor furnace residual heat removal system pipeline equipped with one of a plurality of systems is connected to the nuclear reactor furnace pressure tank. A heat exchanger; a pipe connecting the residual heat removal system of the nuclear reactor and the fuel pool cooling and purification system, a connection pipe of the nuclear reactor residual heat removal system-fuel pool cooling and purification system, which is characterized by having the systems The residual heat removal system of the nuclear reactor has three systems of a first system, a second system, and a third system, wherein the first system uses the heat exchanger of the first system to cool the water supply system of the nuclear reactor or The cooling water circulating to the fuel pool and the second system are cooled and circulated to the fuel pool using a heat exchanger of the second system The cooling water of the third system is also the cooling water circulating to the fuel pool by using the heat exchanger of the third system; and the pipeline of the fuel pool cooling purification system takes water from the fuel pool, and after purification, The suppression pond purification system is circulated to the nuclear reactor well or a machine preset pond. 14. · A method for operating the cooling equipment of a nuclear reactor, which is equipped with 45 papers with the Chinese National Standard (CNS) A4 specification (2) 0 X 297 cm.) ------------ -ill — — — — ·! 1111! 11. (Please read the notes on the back before filling in this page) 8 ο ο / C 0 dfip 386 671 ο 2 6 8888 ABCD VI. Application scope of patents: a nuclear reactor and a A pool valve is constructed between the fuel pools; at least one water source is connected between the nuclear reactor well and the fuel pool and a fuel pool cooling and purifying system pipeline having a chlorine removal device; a nuclear reaction is vertically arranged at the bottom of the nuclear reactor well Furnace pressure tank; a heat exchanger having a nuclear reaction furnace residual heat removal system pipeline connected to the nuclear reaction furnace pressure tank, characterized in that the nuclear reaction furnace residual heat removal system has a first system to a third system Three systems: In the first system to the third system, at least two heat exchangers connected in series are provided. ------------ Clothing -----! Order --------- line (please read the precautions on the back before filling this page) Printed by the Consumer Cooperatives of the Intellectual Property Bureau of the Ministry of Economic Affairs ^ 46 This paper size applies to China National Standard (CNS) A4 specifications ( 2] 0 X 297g
TW090101750A 2000-02-08 2001-01-30 Nuclear reactor cooling apparatus and its operation method TW462063B (en)

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JP2012230066A (en) * 2011-04-27 2012-11-22 Hitachi-Ge Nuclear Energy Ltd Fuel pool cooling system
US9646726B2 (en) * 2013-02-06 2017-05-09 Westinghouse Electric Company Llc Alternate passive spent fuel pool cooling systems and methods
CN104425043B (en) * 2013-08-27 2017-09-19 中广核工程有限公司 The control method and system of the overpressure protection of PIPING OF MAIN LOOPS IN NUCLEAR POWER STATION
CN104157314B (en) * 2014-09-09 2016-08-31 温州志杰机电科技有限公司 A kind of nuclear reactor connects aluminium alloy silicon nitride high pressure cooling device by appointing
CN104240775B (en) * 2014-09-09 2016-08-31 温州志杰机电科技有限公司 A kind of nuclear reactor flange copper alloy aluminum oxide high-pressure chiller
CN104318963B (en) * 2014-09-09 2016-08-31 温州志杰机电科技有限公司 A kind of female thread evanohm carborundum nuclear reactor cooling equipment
CN104934079A (en) * 2015-06-26 2015-09-23 上海核工程研究设计院 Long-term passive emergency water supply system for floating nuclear power plant
CN113871041B (en) * 2021-09-26 2024-05-10 中国原子能科学研究院 Method for installing, removing and replacing control rod assembly

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