公开(公告)号：WO2003001534A1

公开(公告)日：2003-01-03

申请号：PCT/RU2001/000251

申请日：2001-06-26

IPC: G21C7/27

CPC classification number: G21C3/326 ,  G21C7/27 ,  G21Y2002/201 ,  G21Y2002/304 ,  G21Y2002/601 ,  G21Y2004/30 ,  G21Y2004/40 ,  G21Y2004/403 ,  Y02E30/38 ,  Y02E30/39

Abstract: The invention relates to nuclear energy based on the use of thorium as a nuclear fuel. Said invention makes it possible to efficiently control a nuclear reactor by modifying (shifting) a neutron energy spectrum in the active zone of the nuclear reactor, extend the service time of the nuclear reactor to 30-50 years with a single charging of nuclear fuel, practically stop the production of plutonium and other transuranic elements, exclude a sequential radiochemical transformation of spent nuclear fuel (SNF), thereby excluding any external transportation of the SNF and to significantly improve the ecological safety of nuclear energy. Control of the thorium nuclear reactor is carried out by modifying the neutron energy spectrum in the active zone of the reactor by supplying neutron decelerators in the gaseous form thereof at a controlled pressure ranging from a normal value to one hundred and more atmospheres to fuel elements. The inventive fuel assembly for thorium reactors comprises the fuel elements and is provided with a central distributor and/or a peripheral collector for supplying the gaseous neutron decelerators.

Abstract translation: 本发明涉及基于使用钍作为核燃料的核能。 所述发明使得可以通过改变（改变）核反应堆活动区中的中子能谱来有效地控制核反应堆，通过单次充电核燃料将核反应堆的使用时间延长到30-50年， 几乎停止生产钚和其他超铀元素，排除废核燃料（SNF）的顺序放射化学转化，从而排除SNF的任何外部运输，并显着提高核能的生态安全。 钍核反应堆的控制是通过在反应器的有效区域中以在正常值到一百个大气压至燃料元件的受控压力下供给气态的中子减速器来改变反应器活性区中的中子能谱来进行的。 本发明的用于钍反应器的燃料组件包括燃料元件，并且设置有用于供应气态中子减速器的中心分配器和/或外围收集器。

公开(公告)号：WO00058974A1

公开(公告)日：2000-10-05

申请号：PCT/JP1999/001560

申请日：1999-03-26

IPC: G21C17/022 ,  G21C19/28 ,  G21D3/08 ,  G21D1/00

CPC classification number: G21C17/0225 ,  G21C19/28 ,  G21D3/08 ,  G21Y2002/103 ,  G21Y2002/201 ,  G21Y2002/601 ,  G21Y2004/304 ,  G21Y2004/403 ,  Y02E30/40

Abstract: A method of operating a reactor, which can minimize effectively SCC generation and growth in a BWR reactor structural material and reduce a reactor water radioactivity without increasing a dose rate of a main steam system by performing at a proper timing a control for injecting hydrogen while adjusting a reactor water pH to an alkaline side. Specifically, a first invention controls a reactor water pH at room temperature to within a range, 8.5

Abstract translation: 一种操作反应器的方法，其可以有效地最小化最小化碳酸氢溴酸反应器结构材料的生成和生长并降低反应器水的放射性，而不会在适当的时间执行主蒸汽系统的剂量率，同时调节氢气的控制 将反应器水pH调节至碱性侧。 具体地，第一发明在一个操作循环启动操作的初始阶段将反应器水的pH值控制在8.5

公开(公告)号：WO1997009721A1

公开(公告)日：1997-03-13

申请号：PCT/FR1996001354

申请日：1996-09-04

Applicant: COMMISSARIAT A L'ENERGIE ATOMIQUE

Inventor： COMMISSARIAT A L'ENERGIE ATOMIQUE ,  GARNIER, Jean-Claude ,  LANGUILLE, Alain ,  LO PINTO, Pierre ,  ROUAULT, Jacques

IPC: G21C03/18

CPC classification number: G21C3/18 ,  G21Y2002/201 ,  G21Y2002/601 ,  G21Y2004/30 ,  G21Y2004/60 ,  Y02E30/40

Abstract: The object of the invention is the production of a fuel element capable of containing the actinide alone, under conditions ensuring that its integrity is maintained throughout the incineration process and allowing the recovery of the incineration products. This is achieved by an element having a tubular outer sleeve (30) and a tubular inner jacket (38), coaxial with the sleeve, so as to define an annular cavity (44) for receiving actinide particles (46) to be incinerated and a central inner space (42), wherein the inner jacket (38) is made of a material permeable to the incineration gases, but impermeable to actinides, and extends over a portion of the length of the sleeve (30) so as to define at least one expansion chamber (40) with which the central inner space (42) communicates.

Abstract translation: 本发明的目的是在确保在整个焚烧过程中保持其完整性并且允许回收焚化产物的条件下生产能够单独含有锕系元素的燃料元件。 这通过具有与套管同轴的管状外套管（30）和管状内护套（38）的元件来实现，以便限定用于接收待焚烧的锕系颗粒（46）的环形空腔（44）和 中心内部空间（42），其中所述内部护套（38）由对所述焚化气体可渗透的材料制成，但对于锕系元素不可渗透，并且在所述套筒（30）的长度的一部分上延伸以至少限定 一个膨胀室（40）与中心内部空间（42）连通。

公开(公告)号：WO1992001295A1

公开(公告)日：1992-01-23

申请号：PCT/US1991004640

申请日：1991-06-28

Applicant: GENERAL ELECTRIC COMPANY

Inventor： GENERAL ELECTRIC COMPANY ,  DILLMANN, Charles, Warner ,  TOWNSEND, Harold, Edward ,  NESBITT, Loyd, Brice

IPC: G21C09/00

CPC classification number: G21C15/243 ,  G21C1/084 ,  G21C1/28 ,  G21C5/02 ,  G21C9/004 ,  G21C15/24 ,  G21Y2002/201 ,  G21Y2002/601 ,  G21Y2004/40 ,  Y02E30/31

Abstract: The wetwell space in a suppression pool (26) of a nuclear reactor containment is continuously ventilated by exhausting gas therefrom, while at the same time, during normal system operation atmospheric air from a source of same is admitted to the wetwell but such admission being blocked during a LOCA. All exhaust flow from the wetwell is conveyed through a conduit that outlets at a remote elevated location in the atmosphere. All exhaust flow through the conduit (37) is before outletting therefrom passed through gas treatment operation (60) wherein any particulates in the gas mixture are removed. Further treatment of the gas with charcoal to adsorb noble gases can be carried out.

公开(公告)号：WO1992001293A1

公开(公告)日：1992-01-23

申请号：PCT/US1991004635

申请日：1991-06-28

Applicant: GENERAL ELECTRIC COMPANY

Inventor： GENERAL ELECTRIC COMPANY ,  TOWNSEND, Harold, Edward

IPC: G21C07/16

CPC classification number: F04D29/047 ,  F04D7/08 ,  F04D13/043 ,  F04D15/0005 ,  F04D29/426 ,  F04D29/448 ,  G21C1/084 ,  G21C1/28 ,  G21C5/02 ,  G21C15/24 ,  G21C15/243 ,  G21Y2002/201 ,  G21Y2002/601 ,  G21Y2004/40 ,  Y02E30/31

Abstract: A recirculation system (10) is disclosed for driving reactor coolant water in an annular downcomer (118) defined between a reactor vessel and a core shroud (12) spaced radially inwardly therefrom. The system supplies feedwater to the vessel and to a turbopump (18) disposed inside the downcomer (118). The turbopump (18) in accordance with one embodiment of the present invention includes a stationary axle (22) and a pump impeller (26) rotatably joined thereto and having an inlet end for receiving the coolant water from the downcomer. An annular plenum (30) surrounds the impeller for channeling feedwater to a plurality of turbine blades (36) joined to the impeller for rotating the impeller for driving the coolant water. The impeller is lubricated solely by the feedwater upon rotation of the impeller about the axle.

公开(公告)号：WO1992001289A1

公开(公告)日：1992-01-23

申请号：PCT/US1991004633

申请日：1991-06-28

Applicant: GENERAL ELECTRIC COMPANY

Inventor： GENERAL ELECTRIC COMPANY ,  FENNERN, Larry, Edgar ,  DILLMANN, Charles, Warner ,  TOWNSEND, Harold, Edward ,  CHALLBERG, Roy, Clifford ,  WILKINS, Daniel, Raymond ,  NESBITT, Loyd, Brice ,  CONGDON, Steven, Paul ,  FAWCETT, Russell, Morgan ,  GLUNTZ, Douglas, Marvin ,  SIMON, Barry, Howard ,  O'NEIL, Timothy, Joseph

IPC: G21C03/14

CPC classification number: G21C15/243 ,  F04D7/08 ,  F04D13/04 ,  F04D29/605 ,  G21C1/084 ,  G21C1/28 ,  G21C5/02 ,  G21C15/24 ,  G21Y2002/201 ,  G21Y2002/601 ,  G21Y2004/40 ,  Y02E30/31 ,  Y10S376/917

Abstract: A reactor core (104) includes upper and lower matrices of fuel bundles. Fuel rods in the upper matrix (126) have their plenums oriented upward, while fuel rods in the lower matrix (124) have their plenums oriented downward. Refueling involves removal of a first bundle in the upper matrix (126), removal and retirement of the bundle in the lower matrix (124) directly below the original position of the first bundle, inversion and installation of the first bundle in the lower matrix, and installation of a new bundle in the upper matrix. The new bundle is installed plenum-side up. The bi-level core (104) provides greater flexibility in repositioning fuel bundles for longer burnups and lower high-level waste. In particular, problems with axial spectral variations in neutron flux can be compensated using the disclosed core arrangement and refueling procedure.

公开(公告)号：WO2015160407A2

公开(公告)日：2015-10-22

申请号：PCT/US2015/012386

申请日：2015-01-22

Applicant: BODI, Robert, F. ,  STUART, Martin, A.

Inventor： BODI, Robert, F. ,  STUART, Martin, A.

IPC: G21D5/00

CPC classification number: G21C19/48 ,  G21F9/30 ,  G21G1/02 ,  G21Y2002/60 ,  G21Y2002/601 ,  G21Y2004/20

Abstract: A nuclear reactor adapted for generating energy and/or decontaminating nuclear fuel using a plurality of energy beam generating accelerator devices configured for inducing a photo-fission reaction in the nuclear fuel.

Abstract translation: 核反应堆适于使用多个能量束产生加速器装置产生能量和/或净化核燃料，所述能量束产生加速器装置被配置用于引起核燃料中的光裂变反应。

公开(公告)号：WO2009082254A1

公开(公告)日：2009-07-02

申请号：PCT/RU2007/000732

申请日：2007-12-26

Applicant: ТОРИУМ ПАУЭР ИНК. ,  БАШКИРЦЕВ Сергей Михайлович ,  КУЗНЕЦОВ Валентин Федорович ,  КЕВРОЛЕВ Валерий Владимирович ,  МОРОЗОВ Алексей Глебович

Inventor： БАШКИРЦЕВ Сергей Михайлович ,  КУЗНЕЦОВ Валентин Федорович ,  КЕВРОЛЕВ Валерий Владимирович ,  МОРОЗОВ Алексей Глебович

IPC: G21C3/326

CPC classification number: G21C3/08 ,  G21C3/28 ,  G21C3/58 ,  G21C3/60 ,  G21C5/18 ,  G21C5/20 ,  G21Y2002/304 ,  G21Y2002/601 ,  G21Y2004/30 ,  G21Y2004/40 ,  Y02E30/32 ,  Y02E30/38

Abstract: Изобретение относится к конструкциям легководных ядерных реакторов, в которых в качестве топлива применяется торий, в частности, к конструкциям бесчехловых тепловыделяющих сборок, из которых сформированы активные зоны водо-водяных энергетических реакторов, таких как реактор BBЭP-1000. В активной зоне ядерного реактора, содержащей топливную сборку из запального и воспроизводящего модулей, сжигается ториевое топливо в воспроизводящем модуле вместе с обычным реакторным топливом, включающим непрофилированный обогащенный уран или энергетический плутоний в запальном модуле. Запальный модуль содержит пучок топливных элементов, которые имеют трёхлепестковый профиль, образующий винтовые дистанционирующие рёбра. Запальный и воспроизводящий модули могут быть связаны между собой посредством замкового соединения или не иметь жёсткой механической связи. Конструкция топливной сборки в соответствии с изобретением обеспечивает её полную совместимость с существующими топливными сборками, используемыми в реакторах BBЭP-1000. Разборность двухсекционной топливной сборки позволяет обеспечить независимую перегрузку запального модуля.

Abstract translation: 本发明涉及一种使用钍燃料的轻水慢化核反应堆的结构设计，特别涉及构成水慢化发电反应堆（例如WWER-1000反应器）核心的无油燃料组件的结构设计。 育种模块中的钍燃料与在驱动器模块中含有未成形浓缩铀或发电钚的常规反应器燃料一起燃烧在核反应堆的核心中，所述核反应堆的核心包括由驾驶员和育种模块组成的燃料组件。 驱动器模块包括一组形成螺旋间隔肋的三叶形燃料电池。 驾驶员和育种模块可以通过插口接头彼此联接或者不具有刚性机械联接。 燃料组件的本发明的结构设计提供了与WWER-1000反应堆中使用的现有燃料组件的完全兼容性。 可以拆卸两段燃料组件的事实使得可以单独地重新加载驾驶员模块。

公开(公告)号：WO2006072279A1

公开(公告)日：2006-07-13

申请号：PCT/EP2005/012404

申请日：2005-11-19

Applicant: GESELLSCHAFT FÜR SCHWERIONENFORSCHUNG MBH ,  FEHRENBACHER, Georg ,  RADON, Torsten

Inventor： FEHRENBACHER, Georg ,  RADON, Torsten

IPC: G21F3/00 ,  G21F3/04

CPC classification number: G21F3/04 ,  G21F1/12 ,  G21F3/00 ,  G21F7/00 ,  G21Y2002/304 ,  G21Y2002/402 ,  G21Y2002/601 ,  G21Y2004/30

Abstract: Die Erfindung betrifft eine mehrschichtige Strahlenschutzwand zur Abschirmung von Gamma- und/oder Teilchenstrahlung eines Reaktionsplatzes an einer Beschleunigeranlage, wobei die Strahlenschutzwand einen sandwichartigen Aufbau aus zumindest einer ersten und zweiten Schichtanordnung umfasst, wobei die erste Schichtanordnung zumindest eine primäre Abschirmschicht und die zweite Schichtanordnung zumindest eine sekundäre Abschirmschicht umfasst. Dabei ist zumindest eine der ersten und zweiten Schichtanordnungen in eine Mehrzahl Teilabschnitten unterteilt, wodurch eine selektierte Entsorgung ermöglicht wird. Dadurch werden eine gesteigerte Kosteneffizienz erreicht und die Umweltbelastung verringert.

Abstract translation: 本发明涉及一种多层的辐射防护壁用于屏蔽γ和/或加速器安装的反应空间的颗粒，其中所述辐射防护壁包括至少一个第一和第二层的安排，其特征在于，所述第一层布置包括至少一个主屏蔽层和所述第二层布置包括至少一个的夹层状结构 包括第二屏蔽。 在这种情况下，第一和第二层的安排一个被分成至少多个部分，从而使能选择的处置。 这增加的成本就可以实现和减少环境污染。

公开(公告)号：WO2004109715A2

公开(公告)日：2004-12-16

申请号：PCT/US2004/017645

申请日：2004-06-04

Applicant: D.B.I. CENTURY FUELS AND AEROSPACE SERVICES, INC. ,  D'AUVERGNE, Hector, A.

Inventor： D'AUVERGNE, Hector, A.

IPC: G21F9/00

CPC classification number: G21C1/00 ,  G21C1/30 ,  G21C3/62 ,  G21C7/34 ,  G21Y2002/304 ,  G21Y2002/50 ,  G21Y2002/601 ,  G21Y2004/10 ,  G21Y2004/30 ,  G21Y2004/40 ,  Y02E30/37 ,  Y02E30/38 ,  Y02E30/39

Abstract: A nuclear-powered plant for systems of up to about 100 MWs with a confinement section where the reaction takes place in a core having a reactive thorium/uranium-233 composition, and where an external neutron source is used as a modulated neutron multiplier for the reactor core output. The core is housed in a containment structure that radiates thermal energy captured in a multiple-paths heat exchanger. The exchanger heat energy output is put to use in a conventional gas-to-water heat exchanger to produce commercial quality steam.

Abstract translation: 一种用于高达约100MW的系统的核动力装置，具有限制部分，其中反应发生在具有反应性钍/铀-233组成的核心中，并且其中使用外部中子源作为调制中子倍增器 反应堆堆芯输出。 核心容纳在一个容纳结构中，辐射在多路热交换器中捕获的热能。 交换器热能输出用于常规的气 - 水热交换器以产生商业品质的蒸汽。