JP5743381B2 - 不均質系−均質系組み合わせ式原子炉 - Google Patents
不均質系−均質系組み合わせ式原子炉 Download PDFInfo
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- JP5743381B2 JP5743381B2 JP2009055594A JP2009055594A JP5743381B2 JP 5743381 B2 JP5743381 B2 JP 5743381B2 JP 2009055594 A JP2009055594 A JP 2009055594A JP 2009055594 A JP2009055594 A JP 2009055594A JP 5743381 B2 JP5743381 B2 JP 5743381B2
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- 239000007789 gas Substances 0.000 claims description 58
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- 239000012530 fluid Substances 0.000 claims description 20
- 238000004891 communication Methods 0.000 claims description 18
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- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims description 17
- 239000001257 hydrogen Substances 0.000 claims description 17
- 229910052739 hydrogen Inorganic materials 0.000 claims description 17
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- 238000004519 manufacturing process Methods 0.000 claims description 14
- 239000007788 liquid Substances 0.000 claims description 13
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- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 description 1
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- HNPSIPDUKPIQMN-UHFFFAOYSA-N dioxosilane;oxo(oxoalumanyloxy)alumane Chemical compound O=[Si]=O.O=[Al]O[Al]=O HNPSIPDUKPIQMN-UHFFFAOYSA-N 0.000 description 1
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- LFNLGNPSGWYGGD-UHFFFAOYSA-N neptunium atom Chemical compound [Np] LFNLGNPSGWYGGD-UHFFFAOYSA-N 0.000 description 1
- 150000002835 noble gases Chemical class 0.000 description 1
- 229910000510 noble metal Inorganic materials 0.000 description 1
- 239000012074 organic phase Substances 0.000 description 1
- BMMGVYCKOGBVEV-UHFFFAOYSA-N oxo(oxoceriooxy)cerium Chemical compound [Ce]=O.O=[Ce]=O BMMGVYCKOGBVEV-UHFFFAOYSA-N 0.000 description 1
- RVTZCBVAJQQJTK-UHFFFAOYSA-N oxygen(2-);zirconium(4+) Chemical compound [O-2].[O-2].[Zr+4] RVTZCBVAJQQJTK-UHFFFAOYSA-N 0.000 description 1
- 229910052763 palladium Inorganic materials 0.000 description 1
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- 239000000741 silica gel Substances 0.000 description 1
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- 239000000377 silicon dioxide Substances 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 229910000029 sodium carbonate Inorganic materials 0.000 description 1
- HEMHJVSKTPXQMS-UHFFFAOYSA-M sodium hydroxide Substances [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 description 1
- 235000010339 sodium tetraborate Nutrition 0.000 description 1
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- 229940056501 technetium 99m Drugs 0.000 description 1
- VZCYOOQTPOCHFL-UHFFFAOYSA-N trans-butenedioic acid Natural products OC(=O)C=CC(O)=O VZCYOOQTPOCHFL-UHFFFAOYSA-N 0.000 description 1
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- 125000005289 uranyl group Chemical group 0.000 description 1
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Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
- G21G1/04—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators
- G21G1/06—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators by neutron irradiation
- G21G1/08—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators by neutron irradiation accompanied by nuclear fission
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/30—Subcritical reactors ; Experimental reactors other than swimming-pool reactors or zero-energy reactors
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
- G21G1/0005—Isotope delivery systems
-
- 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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma & Fusion (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Chemical & Material Sciences (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Physical Or Chemical Processes And Apparatus (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
本発明によれば、均質な燃料集合体の任意の1つにおける出力密度を制限する不均質格子配列に対して固有の安全特性を持たせる均質な燃料要素が提供される。
本発明によれば、モジュール式で且つメンテナンス目的のために炉心格子から取り外せる、除熱用の還流冷却器、掃気回路、を個別に備える均質な燃料要素が提供される。
原子炉ガス管理システム16が図5及び図9に最も良く例示され、(1)ガス混合物中の含有水素量が下方可燃限界以下に維持されることが保証されるよう、放射線分解ガスと混合させる希釈ガス流れと、(2)水蒸気、溶液噴霧、溶液表面から出現する放射線分解ガス中に同伴されるウラニウム、の除去を支援するための放射線分解ガス混合物の冷却と、を提供するように設計されている。
図9に示すように、燃料集合体18の各サブユニット用の掃気入口ヘッダ56は原子炉ガス管理システム16のチューブの出口から開始されている。
同伴物トラップ58は、同伴液体、ヨウ素蒸気、核分裂ガスの放射性同位元素の固形の娘核種、掃気中の活性粒子を除去する、銀活性化により形成した金属(ステンレス鋼)スポンジからなる。金属スポンジは、核分裂片及びその他粒子を捕捉するための広い触媒性表面を提供する。金属スポンジは、原子炉を出てから水素再結合装置60の入口前に至る平行ガスラインの各々に位置付けた金属チャンバ内に格納される。
NOx除去システム102は、ガス混合物から残留NOxを除去し、かくして下流側設備における腐食の恐れや酸による環境汚染を無くす機能がある。
燃料浄化構造は図14に概略例示され、一連の液体−液体遠心抽出機及びまたは、抽出セクション124、スクラビングセクション126、ストリッピングセクション128にグループ化されるパルスカラム成る。
ストリッピングセクション128では、有機相下のウラニウム及びプルトニウムが希硝酸(〜0.01M)により水性に遠心される。次いでこの有機溶剤形態物は、洗浄セクション132において0.2M炭酸ナトリウム及び希硝酸を順次使用して微量の放射線分解分解生成物や加水分解分解生成物を除去した後、燃料浄化構造内で再使用される。
以上、本発明を実施例を参照して説明したが、本発明の内で種々の変更をなし得ることを理解されたい。
12 炉心
14 炉心冷却システム
16 原子炉ガス管理システム
18 均質な燃料集合体
19 上方プレナム
20 冷却用コイル回路
21 下方プレナム
22 還流冷却コイル回路
23 円筒状容器
24 掃気回路
26 同心供給チューブ
28 冷却水入口
30 出口流れライン
32 掃気入口
38 ドームヘッド構造
40 崩壊タンク
42 サージタンク
44 一次冷却材ポンプ
48 冷却流体ライン
50 ライン
52 孔付きノズル
54 中央制御棒
56 掃気入口ヘッダ
58 同伴物トラップ
60 水素再結合装置
62 ガス冷却−冷却器
64 圧力調整弁
68 軸方向床
70 金属ハウジング
72 入口
74 出口
76 基材粒子
80 疎水性コーティング
82 延長チムニー
84 圧力安全機構
86 圧力安全容器
88 冷却用コイル
90 重力性排出流れ
96 HEPAフィルタ/木炭床
98 容積型コンプレッサ
100 貴ガス保持用タンク
102 NOx除去システム
104 放射性ガス排気システム
108 第1カラム構造
110 第2カラム構造
112 無機のまたは固体のポリマー溶剤
116 交換クロマトグラフィーカラム
118 蒸発器
122 安全貯蔵カラム
124 抽出セクション
126 スクラビングセクション
128 ストリッピングセクション
130 ラフィーネ
132 洗浄セクション
133 制御棒
133S 安全棒
134 心環
135 ライン
136 可変リラクタンス可逆式3相電気モーター
138 空気圧力
139 爆発作動式スクイブ弁
140 溶液タンク
Claims (21)
- 医療用同位元素製造用の液体燃料組み合わせ式の原子炉であって、
a.正規格子状に構成した不均質格子内の共通の上方プレナムにより相互連結した、対
称な均質燃料集合体群を有するモジュール式の炉心と、
b.各均質燃料集合体群用の個別の且つ取り外し自在の、冷却用構造、還流冷却器、掃
気回路と、
c.炉心内の閉じた燃料循環部分と、
d.閉ループ式の原子炉冷却構造と、
e.前記上方プレナムと流体連通する半閉ループ式の放射線分解ガス管理構造と、
を含む原子炉。 - 対称な均質燃料集合体群の各々の内部の燃料集合体が、共通の下方プレナムにより相互
連結される請求項1の原子炉。 - 対称な均質燃料集合体群の全部における内部の燃料集合体が、共通の下方プレナムによ
り相互連結される請求項1の原子炉。 - 燃料集合体を四角形配列した列格子内に配置した請求項1の原子炉。
- 燃料集合体を三角形ピッチ配列した格子内に配置した請求項1の原子炉。
- 前記上方プレナムが、平坦な底部表面及び平坦な上部表面を含み、前記底部表面が、各
燃料集合体用の入口開口、前記上部表面に形成した少なくとも1つの出口開口にして、前
記半閉ループ式の放射線分解ガス管理構造に連結した出口開口、を有する円盤状のハウジ
ングを含む請求項1の原子炉。 - 前記取り外し自在の冷却用構造が、各前記燃料集合体の周囲を伸延するコイル回路を含
む請求項1の原子炉。 - 前記取り外し自在の冷却用構造が入口ヘッダ及び出口ヘッダを更に含み、前記コイル回
路が還流冷却器に連結して前記入口ヘッダ及び出口ヘッダと連通する連続コイルを形成す
る請求項7の原子炉。 - 前記入口ヘッダ及び出口ヘッダを格納した同心供給チューブを更に含む請求項8の原子
炉。 - 前記掃気回路が、個別の且つ取り外し自在の冷却用構造の上方位置にノズルを含む請求
項1の原子炉。 - 前記個別の且つ取り外し自在の冷却用構造が、各燃料集合体の周囲を伸延するコイル回
路を含み、前記ノズルが前記コイル回路と同中心を有する請求項10の原子炉。 - 前記掃気回路が、前記上方プレナムと流体連通する同伴物トラップと、前記同伴物トラ
ップより上流側で且つ同伴物トラップと流体連通する水素再結合装置と、前記水素再結合
装置より上流側で且つ水素再結合装置と流体連通するガス冷却−冷却器と、を更に含む請
求項1の原子炉。 - 前記水素再結合装置が、ハウジング内に収納した触媒粒子を有する軸方向床を含む請求
項12の原子炉。 - 前記ハウジングが入口及び出口を有する請求項13の原子炉。
- 前記ハウジングの入口及び出口の各位置に圧力安全機構と、前記圧力安全機構と流体連
通する圧力安全容器と、を更に含む請求項14の原子炉。 - 前記ガス冷却−冷却器と流体連通するガスフィルタシステムにして、フィルタ床、フィ
ルタ床と流体連通する容積型コンプレッサ、容積型コンプレッサと流体連通するガス保持
タンク、ガス保持タンクと流体連通するNOx除去システム、NOx除去システムと流体
連通する放射性ガス排気システム、を更に含む請求項12の原子炉。 - 炉心と流体連通する複数の第1カラムと、溶剤を収納する複数の分離カラムとを有する
99Mo処理システムを更に含み、前記分離カラムが前記複数の第1カラムと流体連通する
請求項1の原子炉。 - 医療用同位元素製造用の液体燃料組み合わせ式の原子炉であって、
a.均質燃料集合体を有するモジュール式の炉心と、
b.各前記均質燃料集合体を不均質格子内で相互連結する上方プレナムにして、円盤状
のハウジングを有し、前記ハウジングが平坦な底部表面と、平坦な上部表面と、前記平坦
な底部表面に形成され且つ各前記燃料集合体用の入口開口と、前記平坦な上部表面に形成
した少なくとも1つの出口開口と、を含む上方プレナムと、
c.各前記燃料集合体用の、冷却用構造、還流冷却器、掃気回路と、
d.前記炉心内の閉じた燃料循環部分と、
e.閉ループ式の原子炉冷却構造と、
f.前記上方プレナムの前記出口開口と流体連通する半閉ループ式の放射線分解ガス管
理構造と、
を含む原子炉。 - 各前記燃料集合体は共通の下方プレナムにより相互連結される請求項18の原子炉。
- 冷却構造が取り外し自在であり且つ各前記燃料集合体の周囲を伸延するコイル回路を含
み、掃気回路が、個別の各前記冷却用構造の上方位置にノズルを含み、前記ノズルが前記
コイル回路と同中心を有する請求項18の原子炉。 - 医療用同位元素製造用の液体燃料組み合わせ式の原子炉であって、
a.正規格子状に構成した不均質格子内の共通の上方プレナムにより相互連結した、対
称な均質燃料集合体群を有するモジュール式の炉心にして、前記共通の上方プレナムが少
なくとも2つの個別の前記対称な燃料集合体を相互連結する炉心と、
b.各前記燃料集合体群用の、個別の且つ取り外し自在の冷却用構造、還流冷却器、掃
気回路と、
c.前記炉心内の閉じた燃料循環部分と、
d.閉ループ式の原子炉冷却構造と、
e.前記上方プレナムと流体連通する半閉ループ式の放射線分解ガス管理構造と、
を含む原子炉。
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RU2494484C2 (ru) | 2008-05-02 | 2013-09-27 | Шайн Медикал Текнолоджис, Инк. | Устройство и способ производства медицинских изотопов |
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GB201013142D0 (en) | 2010-08-04 | 2010-09-22 | Mallinckrodt Inc | Purification process |
US10032529B2 (en) * | 2010-12-09 | 2018-07-24 | Westinghouse Electric Company Llc | Nuclear reactor internal electric control rod drive mechanism assembly |
US8638898B2 (en) * | 2011-03-23 | 2014-01-28 | Babcock & Wilcox Mpower, Inc. | Emergency core cooling system for pressurized water reactor |
US10734126B2 (en) | 2011-04-28 | 2020-08-04 | SHINE Medical Technologies, LLC | Methods of separating medical isotopes from uranium solutions |
US10332646B2 (en) | 2011-12-05 | 2019-06-25 | Wisconsin Alumni Research Foundation | Apparatus and method for generating medical isotopes |
RU2649662C2 (ru) * | 2012-04-05 | 2018-04-05 | Шайн Медикал Текнолоджиз, Инк. | Водная сборка и способ управления |
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JP5614821B1 (ja) * | 2013-09-24 | 2014-10-29 | 株式会社京都ニュートロニクス | ウラン233製造方法、トリウム核燃料製造方法、医療用ラジオアイソトープ製造方法、及び、医療用ラジオアイソトープ製造用ターゲットプレート製造方法 |
US20160012928A1 (en) * | 2014-07-08 | 2016-01-14 | Westinghouse Electric Company Llc | Targeted Isotope Production System |
PL225474B1 (pl) * | 2014-09-07 | 2017-04-28 | Univ Jagielloński | Urządzenie oraz sposób do nieinwazyjnego wykrywania materiałów niebezpiecznych w środowisku wodnym |
CN107230504A (zh) * | 2016-03-24 | 2017-10-03 | 姚明勤 | 核电站冷却剂乏燃料箱加硼优化设计防腐防爆 |
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CN109979625B (zh) * | 2019-03-28 | 2022-02-18 | 江苏核电有限公司 | 一种测量反应堆堆芯增殖特性对称性的试验方法 |
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