TW218930B - - Google Patents
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- TW218930B TW218930B TW081107758A TW81107758A TW218930B TW 218930 B TW218930 B TW 218930B TW 081107758 A TW081107758 A TW 081107758A TW 81107758 A TW81107758 A TW 81107758A TW 218930 B TW218930 B TW 218930B
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- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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經濟部中央標準局員工消費合作社印製 218930 A6 __B6_ 五、發明説明(1 ) 琎明乏背鲁 核能電廠傳統上之設計在達到長期,安全及可靠之理轉 。為保證安全,電廠所納入之各種系統和程序均代表對預 期之緊急情況仔细研究之结果。在設計方面得注意到理論 或前提,例如,可包括設計之冗餘性,由於核能電廠運轉 經驗之不斷累積,此種冗餘性,已受到最新理轉規律之質 疑。因此研究核能發電之人員不《被呼籲發展改良之運轉 分析模式,找出改良之埋轉因數界限,Μ及進一步因安全 有闞之運轉規定之改變來提高安全度。由於開發或建造新 的核能發電設胞必須要一段很長的時間,例如要花上十年 或更多的時間在這種功夫方面,同時鑑於有無數的核能發 電設施在運轉中,這些研究人員也被要求修正存在已久的 設施來滿足新的埋轉規定檷準。把新開發出來的東西裝到 老的反應器是一件很花不來的事,電力供應要修改*主要 的閥門要更換,不一而足。 核能工業已衍進了多種反應器型式。有一此種反懕器懕 用者頗廣,運轉時在反應器爐心内產生驅動淌輪之蒸氣, 稱為沸水式反應器(Κ下簡稱BWR ) ,BWR之反應器加熱 之水*不僅成為作工之流體,也是反應的媛和繭,連同其 他之參數在内*使其在反應器糸統内之妥菩供應及懕用* 必然成為安全要求,或是政府管制單位諸如(美國)核能 管制委員會(M下簡稱NRC )釐訂規定之主題。 通常BWR糸統之一般構造會包括一直立之反應器壓力容 器,其中包括一下方反懕器核心结椭,其下則為控制棒驅 (請汔閱泣背曲之注&事項再蟥寫本莨) 本紙張尺度適用中國國家標準(CNS)甲4规格(210 X 297公釐) 81.9.20,000 218930 A6Printed by the Staff Consumer Cooperative of the Central Bureau of Standards of the Ministry of Economic Affairs 218930 A6 __B6_ V. Description of the invention (1) Yeming Fangbeilu The traditional design of nuclear power plants has reached a long-term, safe and reliable principle. To ensure safety, the various systems and procedures incorporated in the power plant represent the results of a careful study of anticipated emergency situations. Attention should be paid to theories or premises in design. For example, it may include the redundancy of the design. Due to the continuous accumulation of nuclear power plant operating experience, this redundancy has been questioned by the latest rationale. Therefore, those who study nuclear power generation do not "have been called for the development of an improved operational analysis model to find out the limits of the improved embedding factor, and further improve the safety due to changes in safe and operational regulations." Since it takes a long time to develop or construct a new nuclear power generation unit, for example, it takes ten or more years in this kind of effort, and given that there are countless nuclear power generation facilities in operation, these researchers It was also required to amend the long-standing facilities to meet the new burial requirements. It is very expensive to install newly developed things into the old reactor. The power supply needs to be modified. * The main valves need to be replaced. The nuclear energy industry has evolved into a variety of reactor types. There is a wide range of users of this type of reactor. During operation, the steam that drives the floating wheel is generated in the core of the reactor, which is called the boiling water reactor (hereinafter referred to as BWR). The water heated by the BWR reactor not only becomes The working fluid is also the source and cocoon of the reaction, together with other parameters * making it suitable for supply and use in the reactor system * must be a safety requirement, or a government control unit such as (US) nuclear energy The Regulatory Commission (NRC for short) defines the subject of the regulation. Generally, the general structure of the BWR system will include an upright reactor pressure vessel, which includes a lower ellipse core structure, and the bottom is the control rod drive (please read the note of the melodrama).莨) This paper scale applies the Chinese National Standard (CNS) A 4 specifications (210 X 297 mm) 81.9.20,000 218930 A6
Bf. 五、發明説明(2 ) 動。在反懕器核心上面,依次為汽水分雕器姐合件及一通 至蒸汽出口之蒸汽乾煉器姐合中件。在反應器之周圍為一 屏蔽牆,屏蔽牆之外為乾井抑壓室(濕井)成龜形係 位於下面并包菌乾井。 在比較更典型之BWR設施中,水冷卻劑係在反應器核心 加熱,在反應器壓力容器内升高成為水與水蒸汽之兩相混 合體。此雙相混合體然後往上通遇蒸汽分離器組合件及蒸 汽乾燥器结構而進入通至汽輪機之蒸汽管線。在通過汽輪 機之後,蒸汽被凝结成水,由給水糸統比較大之凝结及給 水泵回到反應器。給水進到反應器之降流區與從蒸汽分離 器及乾燥作用返回之水相混合。在降流區之水被循環經由 垂直定向之再循環泵而回到反應器核心,再循環泵係將水 流導向位於核心側板及容器壁之間之垂直噴射泵。在典型 方式中,此再循環功能係使用兩個顯明的再循環迴路及對 應之再循瓖泵。 經濟部中央標準局員工消費合作社印製 (靖"""背面之事項再塡寫本w) 在遇到某種形式之破裂或偏離而生故陣時(稱為冷卻流 失事故簡稱L0CA),設計者預期反應器内有更高溫度和更 高壓力之水會開始損失。於是便會動用各動安全糸統和程 序,一面圍堵,一面對此LOC A作熱控。在熱控方面,安全 設計了解到水媛和劑之流失雖然終止了核心的反應而消除 了核子事故之可能性•但所生熱之動力,或者反應器内殘 餘之能量仍然大到需要有冷卻控制來避免核心熔化。一般 來說,圍堵體内的水量足夠此用途而有餘,例如抑壓池所 含之水再加上凝結儲存榷。應用此水冷卻劑作安全用途, 二 _·_·4~=« ____ 本紙張尺度適用中國國家標準(CNS)甲4規格(210 X 297公釐〉 81.9.20 000 218930 A6 B6 五、發明説明(3 ) (清t:t1.-vi背面之;i&事項再塡寫本頁) 有多種與安全有關之技術而緊急核心冷卻糸統(下文簡稱 ECCS)已開發成功可經得起L0CA。例如核心噴钃(CS)系 统及低壓注入(LPCI)設施已Μ各種構形演進出來。 L PC I系統例如採用四個泵,遇到有冷卻水流失情形時便 由安全系統放動。在冷卻劑之損失到了一個充分程度時而 壓力槽之懕力仍很高(例如小管線有破損時),自動安全 系統便會消壓反應器槽,允許較低壓力之給水泉工作,Μ 將水引入反應器。因為自循環系統如早先所說明,係照理 想構造來作此用途,故通常係由LPCI糸統使用,在ECCS之 情況下將水引入。 經濟部中央標準局員工消費合作社印製 然而•以前之安全設計認為在L0C Α情況下,再循環迴路 會斷開。因此在此種LOC A狀況下將水泵進該迴路可能無效 。因之LPCI糸統乃被装以一再循環酒路選擇特色,各為、、 迴路選擇理輯〃 Μ避免此種情況。此安全控制檢知破裂之 再循環迴路而發動一程序,利用引動適當的LPCI注入閥, 而將水注入冗餘之未受損之再循環迴路。使用此種LPCI遇 路選擇特色之經驗顯示其很複雑,及不易測試和維持。在 最近按規定要求之情況下,設計必須計及閥失效等情況之 發生。然而,在現行規定下,要能更有效發揮功用,在已 有的設胞上配上新的東西而使之更新的方法作起來很麻煩 也所費不貲,因為牽涉到電纖更換,泉連接等工作。因此 ,研究人員一直在尋求一種方法•可供運轉者Μ機會不需 迴路選擇理輯制度及與之相關之花費,但仍能改良LPCI系 統之可靠性。 ............ ~ 5« ~ 81.9.20,000 本紙張尺度適用中國國家標準(CNS)甲4規格(210 X 297公梦〉 218930 A6 五、發明説明(4) (清先閲''!'-''背面之注念事項再填,寫本頁) 捕連 本發明係针對一LPCI糸統及方法* K備修改注入迴路, 達到傳統沸水式反應器之再循環迴路中有效水冷沸劑注入 ,但不需倚靠複雜之迴路選擇趣輯。本程序是瞭解到再循 環迴路之一已發生破裂或斷裂,而控制同時注入每一再循 環迴路之冷卻劑之速度和量。利用横仿一類的方法,就完 成冷卻劑注入所需之時間,并就注入之流體所需之量,通 過對LPCI糸統需求之分析•可算出注入時之流量率,并決 定及認明必要之冷卻劑之量,使LPCI處理通過簡單的在冷 卻劑注入導管內使用流量率控制水阻之方法而得到控制。 該等水阻可用習知之限流孔來作成,限流孔之大小和形狀 可決定所需之流量率,或者利用注入導管中閥之節流作用 達到相等之结果。在此處理中,交連導管及本來用於再循 環迴路冷卻前注入選擇之相關交連閥均未作用’而僅保持 一開啟狀況。在新法和體制之下’ LCPI修正并不依賴遇路 選擇本來需要之複雜糸統和儀表’硬體之播亂’線路或管 路之重設均很少。 經濟部中央標準局員工消費合作社印製 本發明之另一特色為提供一種低壓冷卻劑注入系統’用 於各種核能發電設胞,其具有一沸水式反應器’具有一反 應器核心和正常之連轉壓力,第一及第二再循環迴路(其 中包括各別之第一及第二再循環泵及可致動之排放閥)’ 一抑壓池水源,一凝结儲存檐’以及一因應冷卻劑潦失事 故而產生一安全输出之安全糸統。本系統包括第一及第二 低壓冷卻劑注入泵,而帶有吸入口及排出口及可由泵水啟 81.9.20,000 本紙張尺度適用中國國家標準(CNS)甲4規格(210 X 297公釐) 218930Bf. V. Description of invention (2) Action. Above the core of the reactor, there are the steam and water engraving device assembly and a steam refining device assembly in the steam outlet. Around the reactor is a shielding wall, and outside the shielding wall is a dry well suppression chamber (wet well). The turtle-shaped system is located below and covers the dry well. In a more typical BWR facility, the water coolant is heated at the core of the reactor and rises into a two-phase mixture of water and steam in the reactor pressure vessel. The two-phase mixture then passes up through the steam separator assembly and steam dryer structure and enters the steam line leading to the steam turbine. After passing through the steam turbine, the steam is condensed into water, which is condensed by the relatively large feedwater system and fed back to the reactor. The feed water enters the downflow zone of the reactor and mixes with the water returning from the steam separator and drying. The water in the downflow zone is circulated back to the reactor core through a vertically oriented recirculation pump. The recirculation pump directs the water flow to a vertical jet pump located between the core side plate and the vessel wall. In a typical way, this recirculation function uses two distinct recirculation circuits and corresponding recirculation pumps. Printed by the Employee Consumer Cooperative of the Central Bureau of Standards of the Ministry of Economic Affairs (Jing " " " the back of the matter will be written again w) When encountering some form of cracking or deviation and giving birth (called cooling loss accident referred to as L0CA) The designer expects that water with higher temperature and higher pressure in the reactor will start to lose. Therefore, it will use various safety systems and procedures to block and control the LOC A thermally. In terms of thermal control, the safety design understands that although the loss of Shuiyuan and the agent has terminated the core reaction and eliminated the possibility of a nuclear accident, the power of the heat generated or the residual energy in the reactor is still large enough to require cooling Control to avoid core melting. Generally speaking, the amount of water in the enclosure is more than enough for this purpose, for example, the water contained in the pressure suppression tank plus the condensation storage. Use this water coolant for safety purposes, 2_ · _ · 4 ~ = «____ The paper scale is applicable to the Chinese National Standard (CNS) A 4 specifications (210 X 297 mm> 81.9.20 000 218930 A6 B6 V. Description of the invention (3) (Clear t: t1.-vi on the back of the; i & matters and write this page) There are a variety of safety-related technologies and the emergency core cooling system (hereinafter referred to as ECCS) has been successfully developed and can withstand L0CA. For example, the core injection system (CS) system and low pressure injection (LPCI) facilities have evolved in various configurations. The L PC I system, for example, uses four pumps and is released by the safety system when it encounters a cooling water loss situation. When the loss of the agent reaches a sufficient level and the force of the pressure tank is still very high (for example, when the small pipeline is damaged), the automatic safety system will depressurize the reactor tank, allowing the lower pressure feed water to work, M will introduce water Reactor. Because the self-circulation system is used for this purpose according to the ideal structure as explained earlier, it is usually used by the LPCI system, and the water is introduced in the case of ECCS. Printed by the Staff Consumer Cooperative of the Central Standards Bureau of the Ministry of Economy. • Previous security settings It is considered that in the case of L0C A, the recirculation circuit will be disconnected. Therefore, under this LOC A condition, pumping water into the circuit may be ineffective. Therefore, the LPCI system is equipped with a recirculating wine road selection feature, each, The circuit selection logic 〃 M avoids this situation. This safety control detects a broken recirculation loop and initiates a procedure that uses the appropriate LPCI injection valve to inject water into the redundant, undamaged recirculation loop. Use The experience of this type of LPCI road selection feature shows that it is very complex, and it is not easy to test and maintain. In the case of the recent requirements according to the regulations, the design must account for the occurrence of valve failures. However, under the current regulations, it is necessary to be more The method of effectively exerting the function of adding new things to the existing design cells and updating them is cumbersome and costly, because it involves work such as electrical fiber replacement and spring connection. Therefore, researchers have been looking for One method • Opportunities available to operators without the need for loop selection and editing systems and the associated costs, but can still improve the reliability of the LPCI system. ............ ~ 5 «~ 81.9 .20,0 00 The size of this paper is in accordance with Chinese National Standard (CNS) A4 specifications (210 X 297 Gongmeng) 218930 A6 5. Description of the invention (4) (Read the notes on the back of ``! '-' 'First, and then write (This page) This invention is based on an LPCI system and method * K prepared to modify the injection circuit to achieve effective water-cooled boiling agent injection in the recirculation circuit of a traditional boiling water reactor, but without relying on complicated circuit selection. This procedure is to understand that one of the recirculation circuits has broken or broken, and to control the speed and amount of coolant injected into each recirculation circuit at the same time. Using a method such as copying, the time required to complete the injection of the coolant, and the amount of fluid required for injection, through the analysis of the needs of the LPCI system, the flow rate at the time of injection can be calculated, and it is determined and recognized as necessary The amount of coolant allows the LPCI treatment to be controlled by simply using a flow rate to control the water resistance in the coolant injection conduit. These water resistances can be made with conventional flow restriction holes. The size and shape of the flow restriction holes can determine the required flow rate, or the throttle effect of the valve in the injection pipe can be used to achieve the same result. In this process, the cross-connecting conduit and the related cross-connecting valve that were originally used for the injection selection before recirculating loop cooling have no effect 'and only maintain an open condition. Under the new law and system, the LCPI amendment does not rely on encountering roads. The complex hardware and instrumentation that were originally required, and the “hardware disturbing” circuit or pipeline are rarely reset. Printed by the Staff Consumer Cooperative of the Central Bureau of Standards of the Ministry of Economic Affairs. Another feature of the present invention is to provide a low-pressure coolant injection system 'used in various nuclear power generation cells, which has a boiling water reactor' with a reactor core and normal connection Turning pressure, the first and second recirculation circuits (including the respective first and second recirculation pumps and actuatable discharge valves) 'a pressure-suppressor water source, a condensed storage eaves' and a corresponding coolant A safety system that produces a safety output in the event of an accident. This system includes the first and second low-pressure coolant injection pumps, with suction inlets and discharge outlets and can be pumped by water 81.9.20,000 This paper size is applicable to China National Standard (CNS) A 4 specifications (210 X 297 mm) 218930
Afi ΒΓ, 五、發明説明(5) (諳先閱4背面之注-事項再堝寫本頁) 動。設有給水導管配置,用流通方式,將第一及第二 低壓冷卻劑泵與抑壓池相耩接。第一及第二冷卻劑注入導 管之設係與第一及第二低壓冷卻劑注入泵相耦接,并通至 各別第一及第二再循環迴路。各別之第一及第二冷卻劑導 管中之第一及第二水阻成份係供限制其中之水冷卻劑流於 一預定之流率’此流率係選來送出一預定最之水冷卻劑至 第一及第二再循環迴路之每一路。流率之選定係在有效從 一個冷卻劑注入導管實反應器核心之緊急冷卻作用。設有 一控制配置,此配置可因應安全输出而引動第一及第二低 壓冷卻劑注入泵。 本發明之另一特色為提供一方法,用以將低壓冷卻水注 入一核能發電設施之沸水式反應器中,核能發電設施中有 一緊急核心冷卻水源,第一及第二獨立之再循環迴路(在 正常情況將水循環通過反應器核心來產生蒸汽),以及一 可因應冷卻水流失事故之安全糸統,以產生一安全输出, 用Μ造成至少有預定量之水冷卻劑供至該反應器,含有以 下之步驟: 從水冷卻劑源提供第一及第二水流路通到各別之第一及 第二再循環迴路; 提供可引動之低壓冷卻劑注入泵,以從該水源泵水通過 第一及第二水流通路; 經濟部中央標準局員工消費合作社印製 提供一閥配置,使之可從閉合之狀況引動到開啟之狀況 ,用Κ在第一及第二水流通路内造成流動; 因應安全输出而引動該閥配置,Μ允許水冷卻劑同時在 81.9.20,000 本紙張尺度適用中國國家標準(CNS)甲4規格(210 X 297公梦) 218930 A6 Bfi 經濟部中央標準局員工消費合作社印製 五、發明説明(6) 第一及第二水流通路之每一路中流動; 因應該安全输出,引動各低壓冷卻劑注入泵;K及 將第一及第二水流路徑中每一個之冷卻水流限制到一預 定之流體流量率,此流量率係經選來输送預定量之水冷卻 麵至每一各別之第一及第二獨立再循環娌路者,前迷流量 率係選來有效從一水流源實現對該反應器核心之緊急冷卻 〇 本發明之另一特色為提供一種低壓冷卻劑注入系統,用 於多種核能發電設施,此類設施中有一帶有反應器核心及 正常運轉壓力之沸水式反應器,第一及第二再循環迴路( 包括各別之第一及第二再循環泵及可致動之排放閥),一 抑懕池水源,一凝結儲存槽,以及一可因懕冷卻劑流失事 故K產生一安全输出之安全系統。本系統包括第一及第二 低壓冷卻劑注入泵,帶有吸入口及排出口及可致動K泵水 。設有給水導管配置,K流體流通方式,將第一及第二低 壓冷卻劑注入泵耦接至抑壓池,并進一步含有交連導管配 置,用Μ選擇互連第一及第二低壓冷卻爾注入泵之排出口 。第一及第二冷卻劑注入導管之設係與第一及第二低壓冷 卻劑注入泵之各別排放出口相耦接*并通至各別之第一及 第二再循環迴路。在各別之第一及第二冷卻劑注入導管内 設有第一及第二低壓冷卻劑注入閥可於閉合及開啟方位之 間啟動。在各別之第一及第二冷卻劑注入導管内進一步設 有第一及第二水阻裝置,Κ限制其中之冷卻水流於一預定 之流賭流量率,此流量率係選來將一預定量之水冷卻劑送 -?t"·".'·"·!之:'·1-事項再場、'"本頁) 本紙張尺度適用中國國家標準(CNS)甲4規格(210 X 297公楚) 81.9.20,000 218930 A6 B6 五、發明説明(7) 到第一及第再循環埋路之每一路,該流量率係遘來從一冷 卻劑注入導管有效實現反應器核心之緊急冷卻。在交連之 導管内設有交連之閥裝置•可引動於開啟與閉合狀況之間 • Μ選擇將第一及第二低壓冷卻繭注入泵之输出通遇選出 之第一及第二冷卻劑注入等管引導至第一及第二再循環迴 路之一。設有一控制裝置,此裝置可因應該安全轤出,W 引動第一及第二低壓冷卻劑注入泵*及第一和第二低壓冷 卻麵注入閥,Μ及在有安全鎗出時保持交連两裝置於開放 規 出 文 下 在 會 分 部 9 見 可 然 顯 已 分 部 的 百 他 其 之 明 。發 況本 狀 合Μ 姐 看 件 參 元 圔 ,。 附 造示合 構例配 镅明請 具說, « 之 成文 構下 法於 方均 與, 統置 糸配發 由之本 係驟解 明步了 發與分 本分充 故部更 是各為 的 巨 與 質 性 之 明 明 說 细诚 詳篛 之BL 下fflj Η 嫌 意 ;示 示之 表路 意埋 示環 之循 計再 設之 種R8 一 相 之兩 物及 築器 建容 器器 懕應 反反 1 1 為為 1 2 圖_ 經濟部中央標準局ΜΚ工消费合作社印製 之 統 糸 入 注 劑 卻 冷 壓 低 一 之 色 特 之 明 發及 本; 了圖 入程 加流 為體 3流 圖意 示 路 遇 裂 分 1 之 統 糸 入 注 劑 卻 冷 壓。 低圖 一 輯 之埋 施之明 設制說 子控畑 核之雄 為正之 4 修明 園入琎 注本 (諳)1閲功背面之注悉事項再塡寫本頁)Afi ΒΓ, Fifth, the description of the invention (5) (Read the note on the back of 4-Matters and then write this page). There is a water supply pipe configuration, and the first and second low-pressure coolant pumps are connected to the pressure suppression pool by means of circulation. The first and second coolant injection pipes are coupled to the first and second low-pressure coolant injection pumps, and lead to the respective first and second recirculation circuits. The first and second water resistance components in the respective first and second coolant conduits are used to restrict the flow of water coolant therein to a predetermined flow rate. This flow rate is selected to send a predetermined maximum water cooling Agent to each of the first and second recirculation loops. The choice of flow rate is effective in the emergency cooling effect of a coolant injected into the conduit and the core of the reactor. There is a control configuration that can activate the first and second low-pressure coolant injection pumps in response to the safety output. Another feature of the present invention is to provide a method for injecting low-pressure cooling water into a boiling water reactor of a nuclear power generation facility. The nuclear power generation facility has an emergency core cooling water source and first and second independent recirculation loops ( Under normal circumstances, water is circulated through the reactor core to generate steam), and a safety system that can respond to the accident of cooling water loss to produce a safe output, using M to cause at least a predetermined amount of water coolant to be supplied to the reactor, Contains the following steps: Provide the first and second water flow paths from the water coolant source to the respective first and second recirculation circuits; Provide a low-pressure coolant injection pump that can be activated to pump water from the water source through the first The first and second water flow paths; printed by the Staff Consumer Cooperative of the Central Standards Bureau of the Ministry of Economic Affairs to provide a valve configuration that can be induced from the closed state to the open state, using K to cause flow in the first and second water flow channels; The valve configuration is triggered by the safe output. Μ allows the water coolant to be at 81.9.20,000 at the same time. The paper standard is applicable to China National Standard (CNS) A 4 specifications (210 X 297 public dreams) 218930 A6 Bfi Printed by the Employee Consumer Cooperative of the Central Bureau of Standards of the Ministry of Economy V. Invention description (6) Flow in each of the first and second water flow paths; due to safe output, each low-pressure coolant injection pump is activated; K and limit the cooling water flow in each of the first and second water flow paths to a predetermined fluid flow rate, which is selected to deliver a predetermined amount of water cooling surface to each of the respective first and second For independent recyclers, the front flow rate is selected to effectively achieve emergency cooling of the reactor core from a water flow source. Another feature of the present invention is to provide a low-pressure coolant injection system for various nuclear power generation facilities In such facilities, there is a boiling water reactor with a reactor core and normal operating pressure, first and second recirculation circuits (including separate first and second recirculation pumps and actuatable discharge valves) , A water source for suppressing the pond, a condensate storage tank, and a safety system that can produce a safe output due to the accidental K loss of the coolant. The system includes first and second low-pressure coolant injection pumps with suction and discharge ports and actuatable K pump water. Equipped with water supply pipe configuration, K fluid circulation method, coupling the first and second low-pressure coolant injection pumps to the pressure suppression tank, and further containing a cross-connected pipe configuration, using M to selectively interconnect the first and second low-pressure coolant injection The discharge port of the pump. The first and second coolant injection conduits are coupled to the respective discharge outlets of the first and second low-pressure coolant injection pumps * and open to the respective first and second recirculation circuits. The first and second low-pressure coolant injection valves are provided in the respective first and second coolant injection conduits to be activated between the closed and open positions. The first and second coolant injection conduits are further provided with first and second water resistance devices, K restricts the flow of cooling water to a predetermined flow rate, which is selected to change a predetermined flow rate Amount of water coolant is sent-? T " · ". '· &Quot; ·! :: ·· 1-item replay,' " this page) This paper scale is applicable to China National Standard (CNS) A 4 specifications ( 210 X 297 Gongchu) 81.9.20,000 218930 A6 B6 V. Description of the invention (7) To each of the first and the first recirculation buried roads, the flow rate is from a coolant injected into the conduit to effectively achieve the core of the reactor Emergency cooling. There are interconnected valve devices in the interconnected ducts • Can be activated between the open and closed conditions • Μ Select the output of the first and second low-pressure cooling cocoon injection pumps to meet the selected first and second coolant injections, etc. The tube leads to one of the first and second recirculation circuits. Equipped with a control device, this device can be safely ejected, W actuates the first and second low-pressure coolant injection pumps * and the first and second low-pressure cooling surface injection valves, Μ and keeps connected when the safety gun is out Under the opening regulations, the device can be seen in the branch 9 of the meeting. The status of the situation is as follows: Sister M looks at the piece of Yuan Yuan. Attached to the example of the configuration of the configuration, please say that, «The written structure of the method is the same as Fang Jun, and the basic system of the distribution of the distribution of the Shitou is clearly explained, and the distribution and the subdivision are filled separately. The gigantic and qualitative clarification of the BL under the flj Η suspicion; the show of the way is buried in the ring, and the ring is rebuilt. The two kinds of R8 and the building of the container are reversible. 1 1 is 1 2 Figure _ The standard injection product printed by the MK Industrial Consumer Cooperative of the Central Bureau of Standards of the Ministry of Economic Affairs but cold-pressed has a unique color and text; The injection system of Shiluyuyu split into 1 was cold pressed. The low picture of the first series of Shi Mingming's design theory, sub-controlling the nuclear male is the positive 4 Xiu Ming Yuan Ruen Note (Note) 1 notes on the back of the book and then write this page)
各纸張尺度適用中國國家標準(CNS)甲4規格(210 X 297公釐) 81.9.20,000 218930 A6 B6 五、發明説明(8) (請^閲‘-';'背面之;1-麥項再塡寫本頁) 低®冷卻劑注入系統(LPCI)必然是配合一核能發電設 施園堵糸統為主之某些保留水之姐件工作。誧參看_1 , 一圍堵體或反應器建築物係大致示於10。此圔内示意表示 者為一有地板14之外牆12。在建築10内為一反應器托架 16·此托架為園繞沸水反應器(BWR )壓力容器即反應器 20之一生物屏蔽牆18之一分件。一乾井示於22處,由一網 結構即牆23所包園及限定。一抑壓室即濕井係示於24處, 為龜形圍繞著乾井22。此抑壓室2 4約有一半充Μ水* Μ蒯 定一抑壓池26· —放氣糸統將乾井22接至涓井24之抑壓池 26。由主要通氣28及29所表示之乾井到濕井之通氣從乾井 22延至抑壓室24,并可看到連至含於抑懕室24空間中之各 別通氣頭30及31。降流管係在32及33處,并從各別之管集 頭30及31下延而終止於抑壓池26之水面下。 萬一在乾井22内有高能量之核態蒸汽供給系統(NSSS) 管路失效時,反懕器之水及/或蒸汽會放人乾井22之大氣 中而造成L0C Α。因增加乾井壓力之結果,乾井内之大氣, 蒸汽及水之混合體會被逼通遢包括主要通氣28及29之通氣 糸統進到抑壓室24中保持之水井26。此水蒸汽會凝結進入 抑壓池26,因而限制了内部園阻壓力,不能凝结之乾并太 氣會被轉移到抑壓室而存於其中。 經濟部中央標準局負工消費合作社印製 次级臑阻體即反應器建築10可進一步包括反應器建築内 之房間如34及35M及燃料更換樓板36等特色。在房間34及 35之間為乏燃料儲存池部份,如37及38處所示。圔上未示 而位於遠處者則為凝液儲榷(CST)。 -1 η -___ 本紙張又度適用中國國家標準(CNS)甲4規格(210 X 297公釐) 81.9.20,000 218930 Α6 Β6 經濟部中央標準局員工消費合作社印製 五、發明説明(9 ) 如Μ上所見,抑壓池26為假想LOCA期間凝结釋放到乾井 中之任何水蒸汽之工具;為熱停備埋轉至衮變熱直接從管 線通到餘熱移除(RHR )熱交換期間反應器核心隔熱冷卻 糸統之散熱器;為核子糸統釋壓安全閥排放之散熱器;以 及為ECCS之水源。此抑壓池亦為正常運轉情況下之散熱器 。在預期之反懕器過渡期間,通過總蒸汽釋氣閥之排洩係 引導至抑颳池,或該蒸汽在排放管線之端部通過一淬熄器 排出并被凝結。 請參看圖2,所設為一與反應器容器26有闞之再循環部 分之極端示意圓。容器20圖示包括一反應器核心44,此核 心係由延伸於核心板46及一頂導件48間之矩陣排列之燃料 組合件所構成,核心44係由位於控制棒導管集合體50中之 各控制棒所控制。控制棒驅動液壓管線及馬達係遇容器 20之底部如52所示通達。包圍核心44及控制棒導件姐合體 50—部分者為一圚桶形圍板54,其功用為引導水冷卻劑在 容器20内循環。關於此點,水係被迫沿園板54及容器20 ( 降流區)間之環向下流,然後被引導向上Μ大致不斷的方 式通過核心4 4。 圖2格外示意描繪本發明之LPCI修正Μ之執行之反應器 水再循環糸統,此糸統之功用在將所需之冷卻劑及嫒和劑 循環通過反應器核心。此糸統在反應器容器外面,由兩個 大體示於56及57處之環路或區所構成,而對每一環路在乾 井22内部設有一泉,分別示於58及60。泵58及60各連同直 接耦接之水冷式馬達共各種闊件一起製造,為簡明計,圖 (清背面之注念事項再塡寫本頁) ^• Τ 本紙張尺度適用中國國家標準(CNS)甲4规格(210 X 2Θ7公釐) 81.9.20,000 摹Λ»外Γ/號费.利申請常 —Α6 71 ^ ά218930 ^ 五、發明説明(π) 中係示為再循環排放閥分別示於62及64及各別之抽吸或闞 斷閥66及68。大體來銳,冗餘之再循環迴路56及57係使循 環水流流過核心44,從核心圍板54及容器20壁間之環或降 流區之降流進行抽吸:大約有三分之一之核心水流涤通過 再循環酒路56及57取自容器20。水流在此等迴路中被泵至 較高之壓力通過一岐管而分佈〔多個管線(未困示)通過 此岐管連接〕并回到容器20,到此後便被引導至-序列之 噴射泵,其中兩個示意於70及72處:當水流導至該等唄射 泵之起始數級時,因動力交換而引致降流區中周圍之水吸 入唄射泵喉,兩水流在此混合,混合流被導入反應器容器 20之下方充氣部。水流然後再向上流遇核心44作熱交換。 給水係通過位於降流區環上面之唄嘴加入此糸統并與降流 之水結合。 低壓冷卻劑注入功能(LPCI)乃殘餘熱排除系统(RHR >之一部分,在有LOC A之情形時,便發生作用,將水通遇 環路56及57注入反懕器核心,選用此冷卻劑输入辦法乃因 此等迴路會本能的將此種緊急冷卻劑置於容器20内正確的 地方。在此棰冷卻劑流失情形之下,反應容器20中 1 , OOOps i (舉例來說)之正常運轉壓力會被釋放一部分( 因為當時之脫鼷)而通過解壓系統:在發生此種情形時, 緊急核心冷卻系統之四涸LPCI泵匣敌動。此等泵在未用於 LPCI之同時,也可用為抑壓池26中之冷卻水Μ及其他之 RHR系统功能(例如園堵體噴羅冷卽,抑壓地噴霧冷卻Μ 及關機冷卻)。然而,在自信號要求LPC 1工作之情況下. -12 -Each paper size applies to China National Standard (CNS) A4 specifications (210 X 297 mm) 81.9.20,000 218930 A6 B6 V. Description of invention (8) (please refer to the back of the '-'; '; 1-Mc item (Let's write this page again) The Low® Coolant Injection System (LPCI) is bound to work with some nuclear water-generating facilities, such as the plugging system of some nuclear power generation facilities. Refer to _1, an enclosure or reactor building is shown roughly in 10. The inside sign is a wall 12 having a floor 14. Inside the building 10 is a reactor bracket 16. This bracket is a part of a biological shielding wall 18 which is one of the reactors 20 which is a pressure vessel of a BWR. A dry well is shown at 22 places, enclosed and limited by a net structure, namely the wall 23. A pressure suppression chamber, or wet well, is shown at 24 places, surrounding the dry well 22 in a turtle shape. About half of this pressure suppression chamber 24 is filled with M water * Μ 蒯. A pressure suppression pool 26 is fixed.-The venting system connects the dry well 22 to the pressure suppression tank 26 of the trickle well 24. The dry-well to wet-well ventilation represented by the main ventilations 28 and 29 extends from the dry well 22 to the suppression chamber 24, and the respective venting heads 30 and 31 connected to the space of the suppression chamber 24 can be seen. The downcomers are at 32 and 33 and extend from the respective headers 30 and 31 and terminate under the water surface of the pressure suppression tank 26. In case of failure of the high-energy nuclear steam supply system (NSSS) pipeline in the dry well 22, the water and / or steam from the reactor will be discharged into the atmosphere of the dry well 22 to cause L0C Α. As a result of increasing the pressure of the dry well, the mixture of atmosphere, steam and water in the dry well will be forced to pass through the ventilation including the main ventilation 28 and 29 into the well 26 maintained in the suppression chamber 24. This water vapor will condense into the suppression tank 26, thus limiting the internal resistance pressure, which cannot be condensed to dryness and the atmosphere will be transferred to the suppression chamber and stored therein. Printed by the National Bureau of Standards of the Ministry of Economic Affairs, the Negative Work Consumer Cooperative. The secondary damper, the reactor building 10, may further include features such as rooms in the reactor building such as 34 and 35M and fuel replacement floor 36. Between rooms 34 and 35 is the portion of spent fuel storage pool, as shown at 37 and 38. Not shown above and those located far away are condensate storage (CST). -1 η -___ This paper is again applicable to the Chinese National Standard (CNS) A 4 specifications (210 X 297 mm) 81.9.20,000 218930 Α6 Β6 Printed by the Employee Consumer Cooperative of the Central Bureau of Standards of the Ministry of Economy V. Description of invention (9) As seen on Μ, the pressure suppression tank 26 is a tool for condensing any water vapor released into the dry well during the LOCA; for the hot standby to be transferred to the gang to change the heat directly from the pipeline to the residual heat removal (RHR) reactor during heat exchange Radiator for core thermal insulation cooling system; radiator for nuclear system pressure relief valve; and water source for ECCS. This suppressor is also a radiator under normal operating conditions. During the expected transition period of the reactor, the discharge through the main steam release valve is directed to the squeegee, or the steam is discharged through a quencher at the end of the discharge line and condensed. Referring to Fig. 2, an extremely schematic circle set as a recirculation part with the reactor vessel 26 is set. The vessel 20 is shown to include a reactor core 44 composed of a fuel assembly extending in a matrix between the core plate 46 and a top guide 48. The core 44 is composed of a control rod conduit assembly 50 Controlled by each control rod. The control rod drives the hydraulic line and the motor to meet the bottom of the container 20 as shown at 52. Surrounding the core 44 and the control rod guide assembly 50-part of which is a bucket-shaped enclosure 54 whose function is to guide the circulation of water coolant in the container 20. At this point, the water system is forced to flow down the circle between the circular plate 54 and the container 20 (downflow zone), and then is directed upward through the core 4 in a substantially constant manner. FIG. 2 particularly schematically depicts the implementation of the reactor water recycling system of the LPCI modification M of the present invention. The function of this system is to circulate the required cooling agent and the agent through the reactor core. This system is outside the reactor vessel and is composed of two loops or zones generally shown at 56 and 57, and for each loop there is a spring inside the dry well 22, shown at 58 and 60, respectively. The pumps 58 and 60 are manufactured together with a wide range of wide-body parts directly coupled with water-cooled motors. For simplicity, the diagram (see the notes on the back side and then write this page) ^ • Τ This paper size applies to the Chinese National Standard (CNS ) A 4 specifications (210 X 2Θ7 mm) 81.9.20,000 GΛ »外 Γ / 号 费. 利 应用 常 —Α6 71 ^ ά218930 ^ V. The description of the invention (π) is shown as a recirculation discharge valve shown in 62 and 64 and the respective suction or pop-off valves 66 and 68. Generally speaking, the redundant recirculation circuits 56 and 57 allow circulating water to flow through the core 44 and draw from the ring or the downflow between the core wall 54 and the wall of the container 20: about three-thirds One of the core water streams is taken from the container 20 through the recirculating wine paths 56 and 57. In these circuits, the water flow is pumped to a higher pressure and distributed through a manifold (multiple lines (not shown) are connected through this manifold) and returned to the container 20, after which it is directed to the -sequence jet Pumps, two of which are shown at 70 and 72: When the water flow is directed to the initial stages of these jet pumps, the surrounding water in the dewatering zone is drawn into the jet pump throat due to power exchange, where the two flows are After mixing, the mixed flow is introduced into the aeration portion below the reactor vessel 20. The water flow then flows upward to meet the core 44 for heat exchange. The water supply system joins the system through the choke located above the ring of the dewatering zone and combines with the dewatering water. The low-pressure coolant injection function (LPCI) is part of the residual heat removal system (RHR >). In the case of LOC A, it will function to inject water through the loop 56 and 57 into the core of the inverter. Choose this cooling The method of inputting the coolant is so that the circuit will instinctively place this emergency coolant in the correct place in the container 20. Under this coolant loss condition, the 1, OOOps i (for example) in the reaction container 20 is normal Part of the operating pressure will be released (because of the uncoupling at that time) and pass through the decompression system: when this happens, the four core LPCI pump casings of the emergency core cooling system will be moved. These pumps are not used for LPCI, but also It can be used as cooling water M in the pressure suppression tank 26 and other RHR system functions (such as spraying cold plugs in the plug, spray cooling M in suppression and shutdown cooling). However, when the self-signal requires LPC 1 to work . -12-
{請先閑讀背面之注意事項再填寫本頁) 甲 4(210X2971'«) 218930(Please read the precautions on the back before filling in this page) A 4 (210X2971 '«) 218930
Αβ BG 經濟部中央標準局負工消費合作社印製 五、發明説明(11) 便在迴路56及57中專用於注人水,如各別之蝓入箭頭74及 75所示。因此冷卻劑可從抑壓池26及設施10已有之代表水 源之凝結儲存槽(未圖示)同時在74及75處注入。然而在 Μ往係對規定或條件作到必要之適應,在此條件下必須假 定迴路56或57之一係斷裂。因此加上了一個壤擇型閥理輯 選擇該仍可作LPCI應用之迴路。如上所述,此一需求乃有 高度複雜之控制和水轉向計劃之需要。 請翻到圖3,此為一示意圖,代表現今某些核能發電設 施中現有低壓冷卻注入糸統所用之開口迴路注入修正( SLIM)。在此匾中,反懕容器80係在壁或結構82所劃定之 乾井内。乾井區内另外示有早先編號56及57所識別之再循 環迴路。此等迴路一如Μ前係K冗餘存在而含有各別之泵 58和60,抽吸闕66和68Κ及排放閥62和64。在下面并包圍 乾井邊界82者為成龜狀之Κ剖面大致示於8 4抑壓池,且園 示接至位於屏蔽體建築内之一緊急核心冷卻糸統(ECCS) 集管箱86。降流管88係從乾井壁82延伸到抑壓池84引道潛 入其中所放出來之液體和蒸汽。 現在朝各低壓冷卻爾注入(LPCI)姐件看,兩泵90a及 91a之抽吸输人係接至ECCS管集箱86,以及經管線92 a及 94a至抑壓池84。一馬達換動之側閥係接至毎一個之输入 ,如分別在96 a及98 a所示。在正常情形閥96 a及98 a均 為敞開。管線94a除了針對ECCS管集箱86外,應注意亦經 管線100 a耦接至方塊102所代表之凝結儲存榷。儲存榷 102通常會在核能電廠設施内裝得比較遠一點,而對於本 本紙張又度適用中國國家標準(CNS)甲4規格(210 X 297公•釐) 81.9.20,000 218930 Λ6 [«; 五、發明説明(12) (清恕問"背',1!>/注悉莽項再塡."'本頁) LPCI糸統而言,係代表一備用水源。泵90a ,91a之輸出 係經各別之管線104 a及106 a通遇一熱交換器傍路閥 108 a ,於閥10δ a敞開時,引導至管線110 a。 從導管110 a出來之水流係引導至導管116 a ,到此其 流動係由一限流孔118 a或等效之水阻所控制,從此處通 過一敞開之LPCI閥120 a而到導管122 a。在閥124 a打 開K及特別是閥128 a及132 a闞閉時,冷卻流乃經由導 管136 a注入排放閥62下游之再循環娌路56中。過到此棰 情況,排放闕62便被闞閉。從管線136 a之注入位置Μ及 排放閥62之閉合,係在假定此再循環管線會發生斷裂之後 Ο 在無事故之情形下抑壓池需要冷卻時•閥90 a及91 a則 致力於使一熱交換迴路工作,將閥108 a闞閉,將流體傍 路,從抑壓池84及管集箱86經導管112 a到熱交換器114 a。冷卻之後液體從此流到導管110 a。在爾要抑壓池冷 卻之情形下,此流體會流過管線即導管110 a而到導管 116 a,從此處通過一敞開之LPCI注入閥120 a而至導管 126a。對於此等正常情況,次一串聯配置之LPCI注入閥 124 a會閉合K達到將冷卻了之流體通遇導管126 a ,冷 卻閥128 a ,管線130 a ,串聯耦合之冷卻閥132 a及管 線134 a而送入84處之抑壓池。 經濟部中央標準局員工消費合作社印製 在抑壓池内於水面Μ上如在84處會經歷到有高壓存在的 情況。此種高壓情況會被蒸汽所引起,因之可應用泵90 a 及91a來行使淬熄作用。闕於這一點,可看出導管140 a 14 ~ 81.9.20,000 本紙張尺度適用中國國家標準(CNS)甲4規格(210 X 297公釐) 218930 Αβ 經濟部中央標準局員工消費合作社印製 五、發明説明(13 ) 係從導管.110 a伸至第一抑壓池注入閥142 a ,此閥在管 線144 a之输出係耦合至次一串聯之抑壓池嗔耪注入閥 146 a ,及從此處經導管148 a至唄隳嘴150 a。 遇到有高壓情況發生在牆82内之園堵體内時可使用相同 形式之淬熄或噴霧。此種淬熄會在變故情況下發揮作用來 保護整個園堵計剿之壓力邊界。因之可看出導管110 a伸 到了一圃阻體哦霧閥154 a ,此閥在管線156 a處之输出 係針對次一串聯之園阻體嗔霧閥,并從此經由并聯之管線 160 a及162 a而到成對之噴霧嘴164 a及166 a。 Μ上就再循環迴路56所述之LPCI分件基本上係對再循瓖 迴路57之對應分件對稱工作。此種共同分件在Μ上就迴路 56所作之說明中係加Μ字尾、'a"來識別。因之用於再循 環酒路57之與之共同之分件在此圖中係Μ同一數字及一字 尾'"b 〃來識別。在每種情況中*雙重或冗餘糸統係配合 ECCS管集箱86,抑壓池84及凝结存儲榷(CST > 102 —起 工作,而Μ上對再循環埋路56之說明亦遘用於再循環迴路 52之相同分件。圈中LPCI糸統之一格外特色在於導管170 a所代表之交連管線,交連閥172 a ,導管174 *交連閥 172 a及管線170 b。此交連管線在早先之糸統中已作過 各種用途,包括將冗餘系統一邊嗔出之水流轉移到另一邊 。沒有此種控制或者沒有本糸统與方法之特色,受壓力之 水在此系統下注入便會取阻力最小之途徑從斷裂之再循環 迴路出來而在未受損之迴路中則失去效力。本發明將早先 之控制系統所有之複雜性一掃而空。在本發明之安排下’ {諳^閲:-背面之注&事項再塡寫本頁) 本紙張尺度適用中國因家標準(CNS>甲4規格(210 X 297公釐) 81·9·20,000 218930 A6 H6 五、發明説明(14 ) (清"閲-择面之注念枣項再塡寫本哀) 交連閥172 a及172 b係不斷留著敞開。對應之下,開口 姐合118 a及118 b之大小係選定來限制或節制冷卻劑水 流到一將預定量之水冷卻劑同時送到毎一獨立之再循環迴 路56及57之流量率。此速率可有效在所需之限時内完成反 應器核心80之緊急冷卻。通過在每一限流孔118 a— 118 b使用水阻所建立之流量率係基於Μ下之認知:⑻對反應 器核心80完成必要之LPCI冷卻所需之流體之量,以及(b)完 成緊急冷卻可Μ用到之時間。分析之下,此水會有充分之 量存在來完成此次任務,因為通到再循環迺路56或57之一 斷裂了之管線中之水係排到乾井中,冷卻劑在此最後流入 至通風口,通過乾井降流區而回到抑壓池。因此提供了單 纯之改正技術,且立即可用Μ改正現有之BWR設施,而改 正所影響到的硬《也極少,不需要重設線路一類的手績, 也不必大規横的管線改裝手鑛。事實上,本修正之LPCI技 術有點消極性。此改良之技術被稱為、、開口酒路注入修正 "(SLIM)。 經濟部中央標準局員工消費合作社印製 請參看圖4,所示為一LPCI SUM理輯圈解。在Μ下之 討論中,目下糸統之共同分件,Κ前用字尾*a"或' 〃識別者僅K相關之數字來表示。圖中方塊和括號190表 示感測參數’内中產生安全输出情況及對應之起始信號。 關於這方面’如理輯圖解位置192所代表,可在反應器 80内檢知一低水位。此情況可以獲致,或如位置194所表 示可檢知一乾池高壓力。此二情況代表冷卻劑流失事故( L 0 C A )之査到。査到後,則如各別之線路1 9 6及1 9 8所表 81.9.20,000 本紙張尺度適用中國國家標準(CNS)甲4規格(210 X 297公梦) 218930 A6 B6 經濟部中央標準局員工消費合作社印製 五、發明説明(15) 示,控制邏輯進行到位置200 ,其中有一備用之柴油引擎 被開機來放動該等馬達及控制此糸統中所應用之閥而作用 之該等禺達或電驅動分件所用之電源。此埋輯圈解區域圖 示在方塊和括號202使閥和泵馬達有電源,及達到、、許可 "標準之目的,後面之情況,對反應器80而言,係發動減 壓或必要之低壓P1及P2之產生。 在柴油引擎發動之動力開始之後,則如在線路204及 206所代表者引至各別之位置208及210 ,乃決定該(等 )用Μ供應電力之匯流排是否有電片在認定之LPCI泵90· 91以及在120 * 124及126及62,64各處之閥。然後,如 在線212及位置214所示,決定在LPCI注入泵90,91是否 有電。同時,如在線216及位置218所示,雖定在LPCI注 入閥120及124有電。此外,如線220及位置222所示, 決定此時在各別之再循環娌路56和57之排放閥62及64處是 否有電。 關於位置218所代表之供電LPCI注入閥120及124之需 求加有一格外之條件。如線224 ,226及位置228所示在 反應器80所顧現之壓力必需降到低於預定之低壓ρ丨。該壓 力例如可在300psi到400psi之範圍。就此•注入閥120及 124乃衹有在二者之間有某一壓力差時才允其工作。 此理輯中在方塊及括號20 2所揭示之另一可許可之條件 係表示在位置230處,在此要決定反應器之壓力是否小於 預先指定之壓力P2,P2之值小於P1之值例如約200psi,若 滿足此條件則邏輯繼纘進行如線232所示。 (^^開^诨曲之^悉"^於塡,寫本") 本紙張尺度適用中國國家標準(CNS)甲4規格(210 X 297公釐) 81.9.20,000 218930 A6 Bfi 經濟部中央標準局員工消費合作社印製 五、發明説明(16) 然後理.輯圃繼鑛進行到方塊及括號234所代表之區域, 以備泵與閥之啟動。所得進一步注意者為理輯画解可Μ垂 直分類。例如,方塊及括號2 36代表各別再循環迴路56及 57—鬮於LPCI泵90,91啟動之區域,而方塊及括號238則 代表IW於注入閥120 * 124開敢之理輯圖解之垂直區域, 方塊及括號240則係代表闞於排放閥62之閉合。因之要注 意* 一決定在位置214所代表之泵90及91有電源存在,則 如線242及位置·246所示,LPCI泵90,91便可供額定水流 之用。此係指該泵之工作已高到額定之速度•此時就水流 而言係Μ額定之容量送水。控制之條件需要在假定L PCI糸 統可應付LOCA之情況以前達到了滿流的情況。 現在指望LPCr注入閥120及124有電,位置228所代表 之壓力許可條件得到滿足,在此兩情形聯合發生如"和〃 線及250所表現者時,理輯流動乃繼續進行如線252及位 置254所表示來認定LPCI注入閥120及124為敝開。同樣 理由,排放閥62 * 6 4亦必須如垂直區内位置256所表示為 閉合。再循環迴路58及60此排放閥之閉合係假定再循環迴 路之破裂會在該等再循環泵之抽吸一邊。因此,LPCI系統 之注入水係針對泵58,60之排放側以及對應之排放閥62 * 64 ^ 最後,一個必要條件為圖解位置246 、254及256所表 示之《況要聯合發生。 由於Μ上之系统及方法,在不違背離本發明所涉及之範 圍之條件下可作某種修正|故望所有包含於以上之說明中 及附圖所示者均應認為是閘釋性而無限制之意。 « — , —„18- 本紙張又度適用中國國家標準(CNS)甲4規格(210 X 297公釐) 81.9.20,000Αβ BG Printed by the Consumer Labor Cooperative of the Central Bureau of Standards of the Ministry of Economy V. Description of the invention (11) It is dedicated to the injection of water in circuits 56 and 57 as shown by the arrows 74 and 75 in the respective worms. Therefore, the coolant can be injected at 74 and 75 simultaneously from the condensate storage tank (not shown) of the pressure suppression tank 26 and the existing water source of the facility 10. However, in the M system, it is necessary to adapt to the regulations or conditions. Under this condition, it must be assumed that one of the circuits 56 or 57 is broken. Therefore, a logic selection valve is added to select a circuit that can still be used for LPCI applications. As mentioned above, this requirement is the need for highly complex control and water diversion plans. Please turn to Figure 3, this is a schematic representation of the open circuit injection correction (SLIM) used in existing low-pressure cooling injection systems in some nuclear power generation facilities. In this plaque, the inverted container 80 is in a dry well defined by a wall or structure 82. The dry well area also shows the recirculation loop identified by the earlier numbers 56 and 57. These circuits, like the M-series K, exist redundantly and contain separate pumps 58 and 60, suction valves 66 and 68K, and discharge valves 62 and 64. The K-shaped section below which surrounds the dry well boundary 82 is a turtle-like shape is shown roughly in the pressure suppression tank and is connected to an emergency core cooling system (ECCS) header 86 located in the shield building. The downcomer 88 extends from the dry well wall 82 to the pressure suppressor 84 to guide the liquid and steam released therein. Now looking at the low-pressure cooling injection (LPCI) components, the suction inputs of the two pumps 90a and 91a are connected to the ECCS header 86, and to the pressure suppression pool 84 via lines 92a and 94a. A motor-operated side valve is connected to each input, as shown at 96 a and 98 a, respectively. Under normal circumstances, valves 96 a and 98 a are open. In addition to the ECCS header 86, the pipeline 94a should be coupled to the condensation storage represented by the block 102 via the pipeline 100a. Storage 102 is usually installed a little further in nuclear power plant facilities, and for this paper, the Chinese National Standard (CNS) A 4 specifications (210 X 297 cm • 8) 81.9.20,000 218930 Λ6 [«; V. Description of the invention (12) (Qing Shu Qin " Back ', 1! ≫ / Note to Mang Xiang Zai. &Quot;' this page) For the LPCI system, it represents a standby water source. The output of the pumps 90a, 91a is passed through the respective pipelines 104a and 106a to meet a heat exchanger bypass valve 108a, and when the valve 10δa is opened, it is led to the pipeline 110a. The water flow from the duct 110 a is guided to the duct 116 a, and the flow is controlled by a restrictor orifice 118 a or equivalent water resistance, from here to the duct 122 a through an open LPCI valve 120 a . When valve 124 a opens K and especially valves 128 a and 132 a are closed, the cooling flow is injected into the recirculation channel 56 downstream of the discharge valve 62 through the guide pipe 136 a. After this situation, the discharge Que 62 was shut off. From the injection position M of the line 136 a and the closing of the discharge valve 62, it is assumed that the recirculation line will break. When the pressure suppression tank needs to be cooled without accidents • Valves 90 a and 91 a are dedicated to The heat exchange circuit works, closing the valve 108 a, and bypassing the fluid from the pressure suppression tank 84 and the header 86 to the heat exchanger 114 a through the conduit 112 a. After cooling, the liquid flows from there to the duct 110a. In the event of cooling of the pressure suppression tank, this fluid will flow through the pipeline 110a to conduit 116a, and from there through an open LPCI injection valve 120a to conduit 126a. For these normal conditions, the LPCI injection valve 124 a in the next series configuration will close K to reach the cooled fluid to meet the conduit 126 a, the cooling valve 128 a, the line 130 a, the series coupled cooling valve 132 a and the line 134 a and sent into the suppression pool at 84 places. Printed by the Employee Consumer Cooperative of the Central Bureau of Standards of the Ministry of Economic Affairs. At the 84 places in the pressure suppression tank, high pressure will be experienced. This high-pressure situation will be caused by steam, so pumps 90a and 91a can be used to exercise the quenching effect. Que at this point, it can be seen that the catheter 140 a 14 ~ 81.9.20,000 The paper size is applicable to the Chinese National Standard (CNS) A 4 specifications (210 X 297 mm) 218930 Αβ Printed by the Employees Consumer Cooperative of the Central Standards Bureau of the Ministry of Economic Affairs Description of the invention (13) extends from the conduit .110 a to the first suppression tank injection valve 142 a, the output of this valve in line 144 a is coupled to the next series suppression tank injection valve 146 a, and from then on From catheter 148 a to whip 150 a. The same form of quenching or spraying can be used when a high-pressure situation occurs in a block inside the wall 82. This kind of quenching will play a role in protecting the pressure boundary of the whole park blockage strategy under the circumstances of accidents. Therefore, it can be seen that the duct 110 a extends to a resistance valve 154 a, and the output of this valve at line 156 a is for the next series connection resistance fog valve, and from then on through the parallel line 160 a and 162 a to the pair of spray nozzles 164 a and 166 a. The LPCI component described on the recirculation circuit 56 at M basically works symmetrically with the corresponding component of the recirculation circuit 57. Such common parts are identified by adding the suffix M and 'a " to the description of circuit 56 on M. Therefore, it is used for recirculating the wine road 57. The common parts are identified by the same number and the suffix '" b 〃 in this figure. In each case, the dual or redundant system is combined with ECCS header 86, suppression tank 84 and condensation storage (CST > 102-work, and the description of reclaimed buried road 56 on Μ Used for the same parts of the recirculation circuit 52. One of the special features of the LPCI system in the circle is the interconnecting pipeline represented by the conduit 170 a, the interconnecting valve 172 a, the conduit 174 * the interconnecting valve 172 a and the pipeline 170 b. This interconnecting pipeline It has been used for various purposes in the earlier system, including transferring the water flowing from one side of the redundant system to the other. Without such control or without the characteristics of this system and method, the water under pressure is injected under this system It will take the path of least resistance out of the broken recirculation loop and lose its effectiveness in the undamaged loop. The present invention wipes out all the complexity of the previous control system. Under the arrangement of the present invention '{谙^ Read: -Notes on the back & write the page again) This paper scale is applicable to the Chinese family standard (CNS> A4 specifications (210 X 297 mm) 81 · 9 · 20,000 218930 A6 H6 V. Description of invention ( 14) (Clear " Read-Select Noodles to Remember Date Items (Re-write the book) The cross-connect valves 172 a and 172 b are kept open. Correspondingly, the sizes of the openings 118 a and 118 b are selected to limit or control the flow of coolant to a predetermined amount of water coolant At the same time, the flow rate is sent to each independent recirculation loop 56 and 57. This rate can effectively complete the emergency cooling of the reactor core 80 within the required time limit. By using water in each flow restriction hole 118 a- 118 b The flow rate established by the resistance is based on the knowledge of: ⑻ the amount of fluid required to complete the necessary LPCI cooling of the reactor core 80, and (b) the time available to complete the emergency cooling. Under analysis, this There will be a sufficient amount of water to complete this task, because the water system in the pipeline that broke into one of the recirculation channels 56 or 57 is discharged into the dry well, where the coolant finally flows into the vent, through the dry The well depressurization zone returns to the suppression pool. Therefore, a simple correction technique is provided, and the existing BWR facility can be corrected immediately with Μ, and the hardship affected by the correction is also very small, and there is no need to reset the line. , There is no need for extensive pipeline changes Hand Mine. In fact, the LPCI technology of this amendment is a bit negative. This improved technique is called ", Open Wine Road Injection Amendment" (SLIM). Printed by the Staff Consumer Cooperative of the Central Standards Bureau of the Ministry of Economic Affairs. Please refer to Figure 4. Shown is an LPCI SUM logical circle. In the discussion under Μ, the common parts of the current system are represented by the suffix * a " or '〃recognizer only K-related numbers. The parenthesis 190 indicates that the safe output condition and the corresponding start signal are generated in the sensing parameter. In this regard, as represented by the logically illustrated position 192, a low water level can be detected in the reactor 80. This situation can be caused or, as indicated by position 194, the high pressure of a dry pond can be detected. These two situations represent the detection of the coolant loss accident (L 0 C A). After the investigation, it is as shown in the table 81.9.20,000 of the respective lines 1 9 6 and 1 9 8 This paper size is applicable to the Chinese National Standard (CNS) A 4 specifications (210 X 297 public dreams) 218930 A6 B6 Central Bureau of Standards of the Ministry of Economic Affairs Printed by Employee Consumer Cooperative V. The description of invention (15) shows that the control logic proceeds to position 200, in which a spare diesel engine is turned on to mobilize the motors and control the valves used in the system. Power supply used by Yuda or electric drive sub-components. This circumscribed area is shown in the box and bracket 202 to enable the valve and pump motor to have power, and to achieve, permit, and "standard" purposes. In the latter case, for the reactor 80, decompression or necessary The generation of low pressure P1 and P2. After the power of the diesel engine is started, as indicated by the lines 204 and 206 to the respective positions 208 and 210, it is determined whether the bus (supplied by M) with electric power has an electric chip in the recognized LPCI Pump 90 · 91 and valves at 120 * 124 and 126 and 62,64. Then, as indicated by line 212 and position 214, it is determined whether the LPCI injection pumps 90, 91 are powered. At the same time, as shown in line 216 and position 218, the LPCI injection valves 120 and 124 are energized. In addition, as indicated by line 220 and position 222, it is determined whether there is electricity at the discharge valves 62 and 64 of the respective recirculation channels 56 and 57 at this time. The requirement for powering LPCI injection valves 120 and 124 represented by position 218 is subject to exceptional conditions. As indicated by lines 224, 226 and position 228, the pressure observed in the reactor 80 must fall below a predetermined low pressure p. The pressure may range, for example, from 300 psi to 400 psi. In this regard, the injection valves 120 and 124 are only allowed to work when there is a certain pressure difference between the two. Another allowable condition disclosed in the box and brackets 20 2 in this rationale is at position 230, where it is determined whether the pressure of the reactor is less than the pre-specified pressure P2, and the value of P2 is less than the value of P1, for example About 200psi, if this condition is met, the logic continues as shown by line 232. (^^ 开 ^ 诨 曲 之 ^^ &^; ^ Yucheng, write a copy ") This paper scale is applicable to the Chinese National Standard (CNS) A 4 specification (210 X 297 mm) 81.9.20,000 218930 A6 Bfi Central Standard of the Ministry of Economic Affairs Printed by the Bureau Staff Consumer Cooperative V. Description of the invention (16) Then, proceed to the area represented by the square and bracket 234 for the start of the pump and valve. Those who draw further attention are the vertical classification of the anatomy. For example, squares and brackets 2 36 represent the respective recirculation loops 56 and 57-the area where the LPCI pumps 90 and 91 are activated, and squares and brackets 238 represent the vertical of the IW at the injection valve 120 * 124 opening the logical illustration The area, the square and the bracket 240 represent the closing of the discharge valve 62. It should be noted that * Once it is determined that there is power supply for the pumps 90 and 91 represented at position 214, then as shown by line 242 and position · 246, the LPCI pumps 90 and 91 are available for rated water flow. This means that the pump's work has been high to the rated speed. At this time, in terms of water flow, it is the M's rated capacity to deliver water. The control conditions need to reach full flow before assuming that the L PCI system can cope with LOCA. Now it is expected that the LPCr injection valves 120 and 124 are powered, and the pressure permission condition represented by position 228 is satisfied. When these two situations occur jointly as shown in the " and 〃 line and 250, the logical flow continues as line 252 And the position 254 indicates that the LPCI injection valves 120 and 124 are open. For the same reason, the discharge valve 62 * 64 must also be closed as indicated by position 256 in the vertical zone. The closing of the discharge valves of the recirculation circuits 58 and 60 assumes that the rupture of the recirculation circuit will be on the suction side of the recirculation pumps. Therefore, the injection water of the LPCI system is directed to the discharge side of the pumps 58, 60 and the corresponding discharge valves 62 * 64 ^ Finally, a necessary condition is that the conditions indicated by the illustrated positions 246, 254, and 256 should occur jointly. Due to the system and method on M, some kind of correction can be made without departing from the scope of the present invention. Therefore, all those included in the above description and shown in the drawings should be considered to be releasable. Unlimited meaning. «—, —„ 18- This paper is again applicable to the Chinese National Standard (CNS) A 4 specifications (210 X 297 mm) 81.9.20,000
Claims (1)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US07/678,384 US5213755A (en) | 1991-04-01 | 1991-04-01 | Low pressure coolant injection modification for boiling water reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
TW218930B true TW218930B (en) | 1994-01-11 |
Family
ID=51347988
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
TW081107758A TW218930B (en) | 1991-04-01 | 1992-09-30 |
Country Status (1)
Country | Link |
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TW (1) | TW218930B (en) |
-
1992
- 1992-09-30 TW TW081107758A patent/TW218930B/zh active
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