JP2013178253A - 原子炉の制御可能な長期運転 - Google Patents
原子炉の制御可能な長期運転 Download PDFInfo
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- 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
- G21C15/24—Promoting flow of the coolant
- G21C15/243—Promoting flow of the coolant for liquids
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- G—PHYSICS
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- G21C—NUCLEAR REACTORS
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- 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
- G21C1/026—Reactors not needing refueling, i.e. reactors of the type breed-and-burn, e.g. travelling or deflagration wave reactors or seed-blanket reactors
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
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- 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
- G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
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- G—PHYSICS
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- G21C15/247—Promoting flow of the coolant for liquids for liquid metals
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- G—PHYSICS
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- 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
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/02—Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
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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
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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
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Abstract
【解決手段】核分裂原子炉炉心から熱を伝達する方法であって、核分裂原子炉炉心における伝搬核分裂爆燃波による核分裂から熱を発生させる工程と、伝搬核分裂爆燃波による核分裂から凝縮相密度流体へと熱を伝達する工程とを含む。
【選択図】図1A
Description
原子炉10の詳細を述べる前に、原子炉10の実施形態の背後にあるいくつかの検討事項を、限定ではなく概要として説明する。原子炉10の実施形態の中には、後述の検討事項を全て満たす内容のものもある。一方、原子炉10の実施形態の中には、後述の検討事項のうち選択されたもののみを満たし、必ずしも全ての検討事項を満たす必要のないものもある。後述の説明には、以下の論文から引用された情報が含まれている:「CompletelyAutomated Nuclear Power Reactors For Long-Term Operation: III. Enabling Technology For Large-Scale, Low-Risk, Affordable Nuclear Electricity」(Edward Teller, Muriel Ishikawa, Lowell Wood, Roderick Hyde, John Nuckolls);「PRESENTED AT theJuly 2003 Workshop of the Aspen Global Change Institute」、University of California Lawrence Livermore National Laboratory publication UCRL-JRNL-122708 (2003)
。(この論文は、Energy, The International Journal(30 November 2003)に提出するために執筆されたものである)。これらの全ての内容はここに説明することによって本願に含まれる。
原子炉10の実施形態の背後にあるいくつかの検討事項を述べたので、さらに、原子炉10の例示的な実施形態について詳述する。原子炉10の例示的実施形態についての以下の説明は、非限定的な例を挙げており、なんら限定するものではないことを強調しておく。上述したように、原子炉10のさらなる態様と同様に、原子炉10のいくつかの実施形態について検討する。原子炉10の例示的な実施形態についての詳細を説明した後、他の実施形態および態様を説明する。
核分裂炉炉心アセンブリ100の中の核分裂爆燃波について説明する。可燃性物質における爆燃波の伝搬によって、予測可能なレベルでエネルギーを解放することができる。さらに、物質構成が必要な時間不変的特徴を有する場合、その後の出力生産が安定したレベルとなる場合がある。最終的に、爆燃波が伝搬する速度を実用的な方法で外部より調節し得る場合、エネルギー解放率および出力生産は所望の状態に制御される。
核分裂炉炉心アセンブリ100およびそこに配置される例示的核燃料チャージの例示的実施形態および態様を説明する。
第1型の第1運転サブシステムを備える第1高速中性子スペクトル核分裂炉心アセンブリを用意する工程と、
上記第1型の第2運転サブシステムを備える第2高速中性子スペクトル核分裂炉心アセンブリを据え付ける工程と、
上記第2高速中性子スペクトル核分裂炉心アセンブリの上記第2運転サブシステムを、上記第1運転サブシステムと連結する工程とを含む方法。
液状の熱吸収物質を、伝搬核分裂爆燃波熱発生領域と熱的接触するように導く工程と、
上記伝搬核分裂爆燃波熱発生領域との熱的接触が実質的にない領域に上記熱吸収物質を流す工程と、
上記伝搬核分裂爆燃波熱生成領域との熱的接触が実質的にない上記領域において、上記熱吸収物質から熱エネルギーを抽出する工程とを含む方法。
非核不活性物質を含む熱吸収物質を、伝搬核分裂爆燃波熱生成領域と熱的接触するように導く工程と、
上記伝搬核分裂爆燃波熱生成領域との熱的接触が実質的にない領域に上記熱吸収物質を流す工程と、
上記伝搬核分裂爆燃波熱生成領域との熱的接触が実質的にない上記領域において、上記熱吸収物質から熱エネルギーを抽出する工程とを含む方法。
核分裂原子炉の炉心における少なくとも一つの場所の温度を検出する工程と、
検出された上記温度に対応する信号を生成する工程と、
上記検知された温度に対応する上記信号を、制御システムへ送信する工程と、
送信された上記信号に対応する上記少なくとも一つの場所に近接する中性子吸収物質の吸収特性を変化させる工程とを含む方法。
炉心領域と、
炉心領域と熱的に結合し、かつ第1流体を含む、第1流体含有構造と、
上記炉心領域から中性子を吸収するように調整され、上記第1流体とは異なる第2流体を含む、第2流体含有構造とを備えた装置。
炉心領域と、
炉心領域と熱的に結合し、第1流体を含む、第1流体含有構造と、
炉心領域から中性子を吸収するように調整され、第1流体と実質的に同位体が同じである第2流体を含む、第2流体含有構造とを備えた装置。
Claims (2)
- 核分裂原子炉炉心から熱を伝達する方法であって、
核分裂原子炉炉心における伝搬核分裂爆燃波による核分裂から熱を発生させる工程と、
伝搬核分裂爆燃波による核分裂から凝縮相密度流体へと熱を伝達する工程とを含む方法。 - 上記凝縮相密度流体は、水、液体金属、テルフェニル、ポリフェニル、フッ化炭素、およびFLIBEを含む群から選択された少なくとも1つの凝縮相密度流体を含む、請求項1に記載の方法。
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US11/605,933 US20080123795A1 (en) | 2006-11-28 | 2006-11-28 | Controllable long term operation of a nuclear reactor |
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EP (1) | EP2097906A4 (ja) |
JP (2) | JP2010511173A (ja) |
KR (1) | KR20090085145A (ja) |
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JP2002071866A (ja) * | 2000-08-30 | 2002-03-12 | Tokyo Inst Of Technol | 原子炉の炉心およびその炉心における核燃料物質の取替方法 |
JP2003021692A (ja) * | 2001-07-09 | 2003-01-24 | Tokyo Inst Of Technol | 原子炉の炉心およびその炉心における核燃料物質の取替方法 |
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JP2020508463A (ja) * | 2017-02-27 | 2020-03-19 | テラパワー, エルエルシー | 原子炉をモデリングするためのシステムおよび方法 |
JP7090096B2 (ja) | 2017-02-27 | 2022-06-23 | テラパワー, エルエルシー | 原子炉をモデリングするためのシステムおよび方法 |
JP2022111366A (ja) * | 2017-02-27 | 2022-07-29 | テラパワー, エルエルシー | 原子炉をモデリングするためのシステムおよび方法 |
JP7358565B2 (ja) | 2017-02-27 | 2023-10-10 | テラパワー, エルエルシー | 原子炉をモデリングするための方法 |
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US9305669B2 (en) | 2016-04-05 |
US20140301522A1 (en) | 2014-10-09 |
JP6026944B2 (ja) | 2016-11-16 |
EP2097906A4 (en) | 2012-08-15 |
CA2670919A1 (en) | 2008-09-04 |
US20080123795A1 (en) | 2008-05-29 |
WO2008105856A2 (en) | 2008-09-04 |
CN101589439B (zh) | 2016-01-13 |
KR20090085145A (ko) | 2009-08-06 |
EP2097906A2 (en) | 2009-09-09 |
JP2010511173A (ja) | 2010-04-08 |
WO2008105856A3 (en) | 2009-01-08 |
CN101589439A (zh) | 2009-11-25 |
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