JP6695804B2 - 鉛冷却形式の高速原子炉の炉心 - Google Patents
鉛冷却形式の高速原子炉の炉心 Download PDFInfo
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- JP6695804B2 JP6695804B2 JP2016548234A JP2016548234A JP6695804B2 JP 6695804 B2 JP6695804 B2 JP 6695804B2 JP 2016548234 A JP2016548234 A JP 2016548234A JP 2016548234 A JP2016548234 A JP 2016548234A JP 6695804 B2 JP6695804 B2 JP 6695804B2
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- 239000000446 fuel Substances 0.000 claims description 207
- 230000002093 peripheral effect Effects 0.000 claims description 16
- WJWSFWHDKPKKES-UHFFFAOYSA-N plutonium uranium Chemical compound [U].[Pu] WJWSFWHDKPKKES-UHFFFAOYSA-N 0.000 claims description 14
- 230000000694 effects Effects 0.000 description 25
- 238000009826 distribution Methods 0.000 description 19
- 239000011800 void material Substances 0.000 description 19
- 230000000712 assembly Effects 0.000 description 13
- 238000000429 assembly Methods 0.000 description 13
- 239000002826 coolant Substances 0.000 description 12
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 8
- 229910052708 sodium Inorganic materials 0.000 description 8
- 239000011734 sodium Substances 0.000 description 8
- 238000004519 manufacturing process Methods 0.000 description 6
- 230000009467 reduction Effects 0.000 description 6
- 239000003758 nuclear fuel Substances 0.000 description 5
- 239000006096 absorbing agent Substances 0.000 description 4
- 239000007789 gas Substances 0.000 description 4
- 238000000034 method Methods 0.000 description 4
- 230000008569 process Effects 0.000 description 4
- 229910052778 Plutonium Inorganic materials 0.000 description 3
- 238000004364 calculation method Methods 0.000 description 3
- 238000010276 construction Methods 0.000 description 3
- 238000011161 development Methods 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 238000009835 boiling Methods 0.000 description 2
- 238000009395 breeding Methods 0.000 description 2
- 230000001488 breeding effect Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000004907 flux Effects 0.000 description 2
- 239000011261 inert gas Substances 0.000 description 2
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 2
- UONOETXJSWQNOL-UHFFFAOYSA-N tungsten carbide Chemical class [W+]#[C-] UONOETXJSWQNOL-UHFFFAOYSA-N 0.000 description 2
- 238000012935 Averaging Methods 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 230000002159 abnormal effect Effects 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- 239000000470 constituent Substances 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 229910001338 liquidmetal Inorganic materials 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000005025 nuclear technology Methods 0.000 description 1
- 238000012856 packing Methods 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 230000000704 physical effect Effects 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 238000001228 spectrum Methods 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
- 238000009827 uniform distribution Methods 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
Images
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/14—Moderator or core structure; Selection of materials for use as moderator characterised by shape
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
- G21C1/022—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders characterised by the design or properties of the core
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/045—Pellets
-
- 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)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Description
ここで、「活性領域における燃料の体積分率」ενは、中性子・物理計算に広く用いられているものである。使用される燃料の密度が理論上の燃料の密度と等しい場合、用語「質量分率」は体積分率に対応する質量分率になる。燃料密度が理論密度と異なる場合、理論密度における質量分率と比較して質量分率が変化した値を記述することになる。
・原子炉全体を通しての鉛の密度の変化に対しての負のボイド効果、
・原子炉全体を通しての鉛の密度の変化に対しての負のボイド反応係数、
・種々の重大な事故での保護の改良を促進する、原子炉の活性域内のかなり減じられた冷却材の密度効果。
・一窒化燃料と同様に高密度燃料、
・比較的高い質量分率、燃料要素の増された直径、等により特徴付けられた活性域の構成、
・活性域の平らにされた幾何学的形状。
・比較的大きい容積と積算電力(integral powers)が得られる極めて平らな活性域、
・比較的小さい容積と単位あたりの電力とを有するモジュラー形態、
計算に従って、密な燃料と、比較的高い質量分率と、かくして、核分裂当たりの比較的高い中性子の発生と、を有する全ての活性域は、実質的に減じられたボイド効果を有している。
以下に、本願出願の当初の特許請求の範囲に記載された発明を付記する。
[1] 筒状の燃料要素の形状が同じシェルに収容された均一なウラン・プルトニウム窒化物燃料を具備し、複数の前記燃料要素は、活性域内の燃料の質量分率が、最低0.305であるように、燃料集合体内に配設され、前記燃料集合体は、活性域の中心部と中間部と周辺部とを形成し、活性域の異なる部分の燃料集合体の燃料要素は、異なる高さの燃料柱を有し、活性域の容積を横切る燃料の半径方向の分布は、これの縦断面で、少なくとも1段を有する階段形状を有している、鉛冷却形式の高速原子炉の活性域。
[2] 前記活性域の容積を横切る燃料の容積質量分率は、最低0.305であり、活性域の前記中心部の直径は、活性域の有効直径の0.4乃至0.5の範囲にあり、活性域の前記中心部の燃料集合体の燃料要素の中の燃料柱の高さは、活性域の前記周辺部の燃料集合体に配設されている燃料要素の中の燃料柱の高さの0.5乃至0.8の範囲内にあり、そして、活性域の有効直径の0.5乃至0.85の範囲の直径を有するように配設された段形状の中間部を形成している燃料集合体の燃料要素の中の燃料柱の高さは、活性域の周辺部の燃料集合体に配設されている燃料要素の中の燃料柱の高さの0.55乃至0.9の範囲に選ばれていることを特徴とする[1]に記載の活性域。
Claims (1)
- 筒状の燃料要素の形状が同じシェルに収容された均一なウラン・プルトニウム窒化物燃料を具備し、複数の前記燃料要素は、炉心の燃料の質量分率が、最低0.305であるように、燃料集合体内に配設され、前記燃料集合体は、炉心の中心部と中間部と周辺部とを形成し、炉心の前記中心部の直径は、炉心の有効直径(D)の0.4乃至0.5の範囲にあり、炉心の前記中心部の燃料集合体の燃料要素の中の燃料柱の高さ(h1)は、炉心の前記周辺部の前記燃料集合体に配設されている燃料要素の中の燃料柱の高さ(H)の0.5乃至0.8であり、そして、炉心の段形状の前記中間部の直径(d2)は、炉心の前記有効直径(D)の0.5乃至0.85の範囲であり、段形状の前記中間部に形成された前記燃料集合体の燃料要素の中の燃料柱の高さ(h2)は、炉心の前記周辺部の燃料集合体に配設されている燃料要素の中の燃料柱の高さの0.55乃至0.9である鉛冷却形式の高速原子炉の炉心。
Applications Claiming Priority (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
RU2014103266/07A RU2549829C1 (ru) | 2014-01-31 | 2014-01-31 | Активная зона реактора на быстрых нейтронах со свинцовым теплоносителем, твэл и тепловыделяющая сборка для ее создания |
RU2014103266 | 2014-01-31 | ||
PCT/RU2014/000897 WO2015115931A1 (ru) | 2014-01-31 | 2014-11-27 | Активная зона реактора на быстрых нейтронах со свинцовым теплоносителем |
Publications (2)
Publication Number | Publication Date |
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JP2017504034A JP2017504034A (ja) | 2017-02-02 |
JP6695804B2 true JP6695804B2 (ja) | 2020-05-20 |
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JP2016548234A Active JP6695804B2 (ja) | 2014-01-31 | 2014-11-27 | 鉛冷却形式の高速原子炉の炉心 |
Country Status (8)
Country | Link |
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US (1) | US9685244B2 (ja) |
EP (1) | EP3101657B1 (ja) |
JP (1) | JP6695804B2 (ja) |
KR (1) | KR101823439B1 (ja) |
CN (1) | CN106133843B (ja) |
CA (1) | CA2937670C (ja) |
RU (1) | RU2549829C1 (ja) |
WO (1) | WO2015115931A1 (ja) |
Families Citing this family (2)
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CN108597625B (zh) * | 2018-05-08 | 2019-04-09 | 西安交通大学 | 一种研究铅基反应堆棒束通道内熔融物迁徙行为的实验装置 |
RU2691628C1 (ru) * | 2018-09-03 | 2019-06-17 | Акционерное общество "Высокотехнологический научно-исследовательский институт неорганических материалов имени академика А.А. Бочвара" | Твэл ядерного реактора |
Family Cites Families (20)
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US3367837A (en) * | 1965-10-24 | 1968-02-06 | Atomic Power Dev Ass Inc | Minimizing the positive sodium void coefficient in liquid metal-cooled fast reactor systems |
US3575803A (en) * | 1968-08-08 | 1971-04-20 | Atomic Energy Commission | Reactor fueling method |
GB1285464A (en) * | 1969-08-08 | 1972-08-16 | Atomic Energy Authority Uk | Improvements in or relating to nuclear reactors |
GB1299768A (en) * | 1969-09-27 | 1972-12-13 | Siemens Ag | Nuclear reactor installations |
US3943036A (en) * | 1969-09-27 | 1976-03-09 | Siemens Aktiengesellschaft | Fast breeder reactor |
US3912583A (en) * | 1973-08-30 | 1975-10-14 | Vladimir Grigorievich Iljunin | Fast-neutron reactor |
JPS5050595A (ja) * | 1973-09-04 | 1975-05-07 | ||
JPS61196195A (ja) * | 1985-02-27 | 1986-08-30 | 株式会社日立製作所 | 高速増殖炉 |
FR2620438B1 (fr) * | 1987-09-11 | 1989-12-01 | Commissariat Energie Atomique | Procede de preparation de nitrure d'uranium et/ou de plutonium utilisable comme combustible nucleaire |
US5162097A (en) * | 1990-07-10 | 1992-11-10 | General Electric Company | Steam cooled nuclear reactor with bi-level core |
US5143690A (en) * | 1990-07-10 | 1992-09-01 | General Electric Company | Fuel-assembly inversion for dual-phase nuclear reactors |
JP3067291B2 (ja) * | 1991-07-25 | 2000-07-17 | 株式会社日立製作所 | 原子炉燃料集合体 |
JP2551892B2 (ja) * | 1992-01-18 | 1996-11-06 | 動力炉・核燃料開発事業団 | 高速炉の中空炉心 |
FR2711835B1 (fr) * | 1993-10-21 | 1995-11-24 | Framatome Sa | Réacteur nucléaire à neutrons rapides dans lequel au moins un élément modérateur est incorporé dans des assemblages du réacteur. |
JPH07120580A (ja) * | 1993-10-22 | 1995-05-12 | Japan Atom Energy Res Inst | 核燃料サイクル |
RU2173484C1 (ru) * | 2000-02-14 | 2001-09-10 | Государственное унитарное предприятие "Научно-исследовательский и конструкторский институт энерготехники" | Быстрый реактор с тяжелым жидкометаллическим теплоносителем |
JP3524884B2 (ja) * | 2001-03-02 | 2004-05-10 | 三菱重工業株式会社 | 高速増殖炉 |
JP4746911B2 (ja) * | 2005-04-27 | 2011-08-10 | 財団法人電力中央研究所 | 高速炉および高速炉施設の建設方法 |
CN101299351B (zh) * | 2008-06-27 | 2011-09-07 | 张育曼 | 水冷双区增殖核反应堆堆芯及采用该堆芯的核反应堆 |
JP2012220325A (ja) * | 2011-04-07 | 2012-11-12 | Toshiba Corp | 高速炉 |
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2014
- 2014-01-31 RU RU2014103266/07A patent/RU2549829C1/ru active
- 2014-11-27 CN CN201480074067.8A patent/CN106133843B/zh active Active
- 2014-11-27 WO PCT/RU2014/000897 patent/WO2015115931A1/ru active Application Filing
- 2014-11-27 JP JP2016548234A patent/JP6695804B2/ja active Active
- 2014-11-27 US US15/112,578 patent/US9685244B2/en active Active
- 2014-11-27 EP EP14881368.6A patent/EP3101657B1/en not_active Not-in-force
- 2014-11-27 CA CA2937670A patent/CA2937670C/en active Active
- 2014-11-27 KR KR1020167020329A patent/KR101823439B1/ko active IP Right Grant
Also Published As
Publication number | Publication date |
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US9685244B2 (en) | 2017-06-20 |
KR101823439B1 (ko) | 2018-01-30 |
JP2017504034A (ja) | 2017-02-02 |
EP3101657A4 (en) | 2017-08-30 |
CN106133843A (zh) | 2016-11-16 |
WO2015115931A1 (ru) | 2015-08-06 |
US20160351278A1 (en) | 2016-12-01 |
EP3101657A1 (en) | 2016-12-07 |
KR20160142277A (ko) | 2016-12-12 |
EP3101657B1 (en) | 2019-04-24 |
WO2015115931A8 (ru) | 2015-10-08 |
CA2937670C (en) | 2017-01-24 |
CA2937670A1 (en) | 2015-08-06 |
CN106133843B (zh) | 2018-09-07 |
RU2549829C1 (ru) | 2015-04-27 |
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R250 | Receipt of annual fees |
Free format text: JAPANESE INTERMEDIATE CODE: R250 |