JP2023517207A - 溶融塩高速炉 - Google Patents
溶融塩高速炉 Download PDFInfo
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- JP2023517207A JP2023517207A JP2022553676A JP2022553676A JP2023517207A JP 2023517207 A JP2023517207 A JP 2023517207A JP 2022553676 A JP2022553676 A JP 2022553676A JP 2022553676 A JP2022553676 A JP 2022553676A JP 2023517207 A JP2023517207 A JP 2023517207A
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- 150000003839 salts Chemical class 0.000 claims abstract description 26
- 239000000446 fuel Substances 0.000 claims abstract description 24
- 239000000203 mixture Substances 0.000 claims abstract description 17
- 239000002826 coolant Substances 0.000 claims abstract description 11
- 229910052768 actinide Inorganic materials 0.000 abstract description 11
- 150000001255 actinides Chemical class 0.000 abstract description 10
- 230000003111 delayed effect Effects 0.000 abstract description 9
- 238000001228 spectrum Methods 0.000 description 4
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 3
- 229910002804 graphite Inorganic materials 0.000 description 3
- 239000010439 graphite Substances 0.000 description 3
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 2
- 239000006096 absorbing agent Substances 0.000 description 2
- 239000002131 composite material Substances 0.000 description 2
- 238000001816 cooling Methods 0.000 description 2
- 239000011258 core-shell material Substances 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 238000003780 insertion Methods 0.000 description 2
- 230000037431 insertion Effects 0.000 description 2
- 229910052751 metal Inorganic materials 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- 238000009877 rendering Methods 0.000 description 2
- 238000004904 shortening Methods 0.000 description 2
- 229910052580 B4C Inorganic materials 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- -1 actinides fluoride Chemical class 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 description 1
- 230000005587 bubbling Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 230000008030 elimination Effects 0.000 description 1
- 238000003379 elimination reaction Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 239000012774 insulation material Substances 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 229910052759 nickel Inorganic materials 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
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- 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
- G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
- G21C1/326—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed next to or beside the core
-
- 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
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/22—Heterogeneous reactors, i.e. in which fuel and moderator are separated using liquid or gaseous fuel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C11/00—Shielding structurally associated with the reactor
- G21C11/06—Reflecting shields, i.e. for minimising loss of neutrons
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/10—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from reflector or thermal shield
-
- 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
- G21C3/44—Fluid or fluent reactor fuel
- G21C3/54—Fused salt, oxide or hydroxide compositions
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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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
本発明は原子力工学の分野に関し、特に溶融塩原子炉に関する。
溶融塩原子炉の主な問題の1つは、実効遅延中性子分率の大きな損失であり、それが、制御された核分裂連鎖反応のプロセスにおけるマイナーアクチニドの燃焼中の原子炉の制御性が劣ることにつながる。原子炉の寿命時間の始まりにおいて、βeff(S)=0.0023である。寿命の終わりにおける、βeffはマイナーアクチニドのみによって決定され、βeff(E)=0.0009に低下する。原子炉周期Trは少なくとも10秒であるべきである。これが、0.0004以下であるべき挿入リアクタンス(insertion reactance)Δk/kに制限を課す。それにもかかわらず、挿入リアクタンスはβeffよりも大きくなければならず、そわなければ、即発の中性子炉の暴走(runway)が生じる。このため、βeff(S)-Δβeff>0.0004、βeff(E)-Δβeff>0.0004という、実効遅延中性子分率の損失値Δβeffを確保しなければならない。
技術的な目的は、少量のフッ化アクチニドの高い溶解度を有するLiF+NaF+KF(FLiNaK)担体塩に基づく燃料組成物を使用する一体型溶融塩高速炉(MSFR)を開発することであり、放射性燃料組成物の容量を最小寸法内に定めることを可能にし、一次回路からの実質的な直径の長い循環配管を排除することを可能にする。
本発明の本質を図1~5に説明する:
図1は、原子炉の3Dモデルを示す;
図2は、原子炉の上面図の3Dモデルを示す(原子炉の蓋は示されていない);
図3は、MSFRの構成を示す;
図4は、原子炉のA-A断面図を示す;
図5は、原子炉のB-B断面を示す。
したがって、提案された原子炉の構成は、放射と熱との保護、制御及び保護システムのアセンブリを有し、駆動部、及び操作要素、中性子源、部分的な側部反射体を含み、一次/二次回路の熱交換器が、炉心のシェルに対して同一平面上に位置する側部反射体のセクション間に配置され、以下のことを可能にする:
1.炉心外での燃料循環時間の短縮に寄与する遅延中性子の実効分率の低減;
2.遅延中性子の実効分率の損失を減らすことによる原子炉の柔軟性の改善;
3.FLiNaK担体塩の選択及び炉心における高速中性子スペクトルの実装により、使用済み核燃料からの大量のマイナーアクチニドの燃焼をもたらす。
Claims (3)
- 循環する燃料組成物を有する一体型溶融塩高速炉であって、
二次回路のパイプラインの入口及び出口と、溶融塩冷却材を初期充填及び補充するための接続パイプとを有する容器と、
一次/二次回路の複数の熱交換器と、
側部反射体、上部反射体、及び下部反射体と、
シェルを有する炉心と、
主循環ポンプとを備え、
前記側部反射体は、前記一次/二次回路の複数の熱交換器が設置された間における複数のセクションで構成されることで、前記炉心の前記シェルに対して同一平面上に位置することを特徴とする一体型溶融塩高速炉。 - 前記下部反射体は、
前記一次/二次回路の複数の熱交換器を設置するための側部切欠きと、
前記炉心内の燃料組成物の使用量の分布プロファイルを整列させるための開口部がその上に設けられた管板とを有し、
前記炉心の前記上部反射体には、前記制御及び防護システムの前記操作要素、並びに中性子源をその中に設置するための開口部が設けられ、
前記側部反射体の前記上部には、前記炉心と、前記主循環ポンプの前記収集チャンバとを接続するように設けられた管に属する開口部が形成されていることを特徴とする請求項1に記載の溶融塩高速炉。 - 前記一次/二次回路の複数の熱交換器が、それらの上部において、前記主循環ポンプの前記加圧チャンバに接続され、その下部において、それらが炉心のマニホルドに接続され、前記一次/二次回路のそれぞれの熱交換器の上部において、溶融塩冷却材を供給及び除去するための二次回路のパイプラインの入口及び出口があることを特徴とする請求項1に記載の溶融塩高速炉。
Applications Claiming Priority (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
RU2020109954 | 2020-03-06 | ||
RU2020109954A RU2733900C1 (ru) | 2020-03-06 | 2020-03-06 | Быстрый жидко-солевой реактор |
PCT/RU2020/000495 WO2021177849A1 (ru) | 2020-03-06 | 2020-09-28 | Быстрый жидко-солевой реактор |
Publications (2)
Publication Number | Publication Date |
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JP2023517207A true JP2023517207A (ja) | 2023-04-24 |
JP7416544B2 JP7416544B2 (ja) | 2024-01-17 |
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JP2022553676A Active JP7416544B2 (ja) | 2020-03-06 | 2020-09-28 | 溶融塩高速炉 |
Country Status (6)
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US (1) | US20230114117A1 (ja) |
JP (1) | JP7416544B2 (ja) |
KR (1) | KR20220152551A (ja) |
CN (1) | CN115461824A (ja) |
RU (1) | RU2733900C1 (ja) |
WO (1) | WO2021177849A1 (ja) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
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CN113488205B (zh) * | 2021-07-27 | 2023-08-15 | 西南科技大学 | 一种具有展平堆芯轴向功率功能的非均匀管式ma嬗变棒 |
Family Cites Families (7)
Publication number | Priority date | Publication date | Assignee | Title |
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RU2088981C1 (ru) * | 1996-02-01 | 1997-08-27 | Государственный научный центр Российской Федерации - Физико-энергетический институт | Ядерный реактор на быстрых нейтронах с жидкометаллическим теплоносителем |
RU2173484C1 (ru) * | 2000-02-14 | 2001-09-10 | Государственное унитарное предприятие "Научно-исследовательский и конструкторский институт энерготехники" | Быстрый реактор с тяжелым жидкометаллическим теплоносителем |
RU2253912C1 (ru) * | 2004-03-23 | 2005-06-10 | Ломидзе Валерий Лаврентьевич | Гомогенный быстрый реактор-хранилище |
EP2674948A4 (en) * | 2011-02-10 | 2017-11-22 | Tokyo Institute of Technology | Nuclear reactor and power generation facility |
US9589680B2 (en) * | 2013-01-18 | 2017-03-07 | Korea Atomic Energy Research Institute | Nuclear fuel rod for fast reactors including metallic fuel slug coated with protective coating layer and fabrication method thereof |
AU2017261230B2 (en) | 2016-05-02 | 2022-02-24 | Terrapower, Llc | Improved molten fuel reactor thermal management configurations |
KR20180019134A (ko) * | 2018-02-05 | 2018-02-23 | 이우성 | 해양원전용 핵폐기물처리 이중구조 고속증식로 원자로설비 |
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2020
- 2020-03-06 RU RU2020109954A patent/RU2733900C1/ru active
- 2020-09-28 JP JP2022553676A patent/JP7416544B2/ja active Active
- 2020-09-28 US US17/905,647 patent/US20230114117A1/en active Pending
- 2020-09-28 CN CN202080098131.1A patent/CN115461824A/zh active Pending
- 2020-09-28 WO PCT/RU2020/000495 patent/WO2021177849A1/ru active Application Filing
- 2020-09-28 KR KR1020227034648A patent/KR20220152551A/ko unknown
Also Published As
Publication number | Publication date |
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JP7416544B2 (ja) | 2024-01-17 |
WO2021177849A1 (ru) | 2021-09-10 |
KR20220152551A (ko) | 2022-11-16 |
CN115461824A (zh) | 2022-12-09 |
US20230114117A1 (en) | 2023-04-13 |
RU2733900C1 (ru) | 2020-10-08 |
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