CN102460596A - 行波核裂变反应堆、燃料组件以及控制其中燃耗的方法 - Google Patents

行波核裂变反应堆、燃料组件以及控制其中燃耗的方法 Download PDF

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Publication number
CN102460596A
CN102460596A CN2010800250562A CN201080025056A CN102460596A CN 102460596 A CN102460596 A CN 102460596A CN 2010800250562 A CN2010800250562 A CN 2010800250562A CN 201080025056 A CN201080025056 A CN 201080025056A CN 102460596 A CN102460596 A CN 102460596A
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China
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burnfront
neutron
neutron flux
location
block
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Pending
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CN2010800250562A
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English (en)
Chinese (zh)
Inventor
C.E.阿尔菲尔德
J.R.吉尔兰德
R.A.海德
M.Y.艾什卡瓦
D.G.麦卡利斯
N.P.迈尔沃尔德
C.惠特默
小洛厄尔.L.伍德
G.B.齐默尔曼
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TerraPower LLC
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Searete LLC
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Priority claimed from US12/384,669 external-priority patent/US8942338B2/en
Application filed by Searete LLC filed Critical Searete LLC
Publication of CN102460596A publication Critical patent/CN102460596A/zh
Pending legal-status Critical Current

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    • 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
    • G21C1/026—Reactors not needing refuelling, i.e. reactors of the type breed-and-burn, e.g. travelling or deflagration wave reactors or seed-blanket reactors
    • 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
    • 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
    • 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
    • G21C1/024—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders characterised by the design or properties of the core where the core is divided in zones with fuel and zones with breeding material
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42—Reprocessing of irradiated fuel
    • G21C19/50—Reprocessing of irradiated fuel of irradiated fluid fuel, e.g. regeneration of fuels while the reactor is in operation
    • 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
    • G21C3/06—Casings; Jackets
    • G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/18—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone
    • G21C5/20—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone wherein one zone contains fissile material and another zone contains breeder material
    • 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
    • G21C7/08—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 by displacement of solid control elements, e.g. control rods
    • 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
    • G21C7/08—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 by displacement of solid control elements, e.g. control rods
    • G21C7/10—Construction of control elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/34—Control of nuclear reaction by utilisation of a primary neutron source
    • 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
    • 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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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Metallurgy (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
CN2010800250562A 2009-04-06 2010-04-02 行波核裂变反应堆、燃料组件以及控制其中燃耗的方法 Pending CN102460596A (zh)

Applications Claiming Priority (5)

Application Number Priority Date Filing Date Title
US12/384,669 US8942338B2 (en) 2009-04-06 2009-04-06 Traveling wave nuclear fission reactor, fuel assembly, and method of controlling burnup therein
US12/384,669 2009-04-06
US12/459,591 US9281083B2 (en) 2009-04-06 2009-07-01 Traveling wave nuclear fission reactor, fuel assembly, and method of controlling burnup therein
US12/459,591 2009-07-01
PCT/US2010/001006 WO2010147615A1 (en) 2009-04-06 2010-04-02 A traveling wave nuclear fission reactor, fuel assembly, and method of controlling burnup therein

Publications (1)

Publication Number Publication Date
CN102460596A true CN102460596A (zh) 2012-05-16

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CN2010800250562A Pending CN102460596A (zh) 2009-04-06 2010-04-02 行波核裂变反应堆、燃料组件以及控制其中燃耗的方法
CN201080025043.5A Expired - Fee Related CN102804282B (zh) 2009-04-06 2010-04-02 行波核裂变反应堆

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CN201080025043.5A Expired - Fee Related CN102804282B (zh) 2009-04-06 2010-04-02 行波核裂变反应堆

Country Status (7)

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US (2) US9281083B2 (enExample)
EP (2) EP2417604A4 (enExample)
JP (4) JP6125840B2 (enExample)
KR (2) KR101887240B1 (enExample)
CN (2) CN102460596A (enExample)
RU (2) RU2527425C2 (enExample)
WO (2) WO2010147615A1 (enExample)

Cited By (3)

* Cited by examiner, † Cited by third party
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CN105427898A (zh) * 2015-12-09 2016-03-23 中国原子能科学研究院 一种多分区模式的行波式焚烧长寿命堆芯
CN107210069A (zh) * 2014-12-31 2017-09-26 泰拉能源公司 通量移位的反应性控制系统
CN109086506A (zh) * 2018-07-20 2018-12-25 西安交通大学 一种适用于液态燃料熔盐堆的燃耗分析计算方法

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CN102696074B (zh) 2009-11-02 2015-11-25 泰拉能源有限责任公司 驻波核裂变反应堆及操作方法
US10008294B2 (en) 2009-11-06 2018-06-26 Terrapower, Llc Methods and systems for migrating fuel assemblies in a nuclear fission reactor
US9922733B2 (en) 2009-11-06 2018-03-20 Terrapower, Llc Methods and systems for migrating fuel assemblies in a nuclear fission reactor
US9799416B2 (en) 2009-11-06 2017-10-24 Terrapower, Llc Methods and systems for migrating fuel assemblies in a nuclear fission reactor
US9786392B2 (en) 2009-11-06 2017-10-10 Terrapower, Llc Methods and systems for migrating fuel assemblies in a nuclear fission reactor
CN102714064B (zh) * 2009-11-06 2015-11-25 泰拉能源有限责任公司 核裂变行波反应堆及迁移燃料组件的系统
WO2012060880A2 (en) * 2010-11-02 2012-05-10 Searete Llc Standing wave nuclear fission reactor and methods
CN104064228B (zh) * 2014-05-16 2016-03-23 中国核动力研究设计院 行波堆启堆区及行波堆启堆区制造方法
JP6682505B2 (ja) * 2014-08-28 2020-04-15 テラパワー， エルエルシー 高速核分裂原子炉および核分裂原子炉の操作方法
CN104926304B (zh) * 2015-06-23 2017-11-07 山东大学 一种氧化钆陶瓷及其制备方法
CN107578825A (zh) * 2017-09-19 2018-01-12 中广核研究院有限公司 反应堆堆芯结构及其启停堆控制方式
CN107977504B (zh) * 2017-11-28 2021-03-16 广东核电合营有限公司 一种非对称堆芯燃料管理计算方法、装置及终端设备
CN109273119B (zh) * 2018-09-13 2022-02-11 中国核动力研究设计院 在临界装置上测量大反应性时优化中子探测器位置的方法
EP3839979B1 (en) 2019-12-17 2022-08-24 Framatome Method of determination of a nuclear core loading pattern
GB202014182D0 (en) * 2020-09-09 2020-10-21 Scott Ian Richard Nuclear reactor passive reactivity control system
CN115050493B (zh) * 2022-06-27 2024-08-09 中国核动力研究设计院 一种压水堆燃料棒包壳材料辐照考验方法
GB2628903A (en) * 2024-03-08 2024-10-09 Rolls Royce Submarines Ltd Nuclear fission power plant
GB2628909A (en) * 2024-03-08 2024-10-09 Rolls Royce Submarines Ltd A nuclear fission power plant
CN119476012B (zh) * 2024-11-06 2025-11-28 南京航空航天大学 一种超临界二氧化碳反应堆少群能群结构优化方法

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Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107210069A (zh) * 2014-12-31 2017-09-26 泰拉能源公司 通量移位的反应性控制系统
CN107210069B (zh) * 2014-12-31 2020-07-24 泰拉能源公司 通量移位的反应性控制系统
CN105427898A (zh) * 2015-12-09 2016-03-23 中国原子能科学研究院 一种多分区模式的行波式焚烧长寿命堆芯
CN105427898B (zh) * 2015-12-09 2017-09-12 中国原子能科学研究院 一种多分区模式的行波式焚烧长寿命堆芯
CN109086506A (zh) * 2018-07-20 2018-12-25 西安交通大学 一种适用于液态燃料熔盐堆的燃耗分析计算方法

Also Published As

Publication number Publication date
US20160196883A1 (en) 2016-07-07
KR20120006533A (ko) 2012-01-18
RU2517359C2 (ru) 2014-05-27
EP2417604A1 (en) 2012-02-15
CN102804282A (zh) 2012-11-28
CN102804282B (zh) 2015-11-25
JP2012523008A (ja) 2012-09-27
JP6125839B2 (ja) 2017-05-10
KR101887240B1 (ko) 2018-08-09
WO2010147614A1 (en) 2010-12-23
EP2417605A4 (en) 2013-01-09
KR20120023636A (ko) 2012-03-13
RU2011143468A (ru) 2013-05-20
JP2012523007A (ja) 2012-09-27
US10186333B2 (en) 2019-01-22
JP6125840B2 (ja) 2017-05-10
RU2527425C2 (ru) 2014-08-27
EP2417604A4 (en) 2013-01-09
US9281083B2 (en) 2016-03-08
EP2417605A1 (en) 2012-02-15
JP2016128829A (ja) 2016-07-14
US20100254502A1 (en) 2010-10-07
WO2010147615A1 (en) 2010-12-23
RU2011143460A (ru) 2013-05-20
KR101715419B1 (ko) 2017-03-10
JP2016128828A (ja) 2016-07-14

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