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1. 发明公开

EP3241216A1 FLUX-SHIFTING REACTIVITY CONTROL SYSTEM 有权转让
标题翻译：通量变换反应控制系统
公开(公告)号：EP3241216A1
公开(公告)日：2017-11-08
申请号：EP15825899.6
申请日：2015-12-30
申请人： TerraPower LLC
发明人： CHEATHAM III, Jesse R.
IPC分类号： G21C1/02 , G21C7/08 , G21C7/18 , G21D3/08
CPC分类号： G21C7/12 , G21C1/026 , G21C7/08 , G21C7/18 , G21D3/08 , Y02E30/34 , Y02E30/39
摘要： A control assembly for a nuclear reactor includes a first reactivity control assembly having a first neutron modifying material, a second reactivity control assembly having a second neutron modifying material, and at least one drive mechanism coupled to the first neutron modifying material and the second neutron modifying material. The first neutron modifying material and the second neutron modifying material are selectively repositionable relative to a fuel region of the nuclear reactor. The at least one drive mechanism is configured to provide the first neutron modifying material and the second neutron modifying material in different directions through the fuel region thereby shifting a flux distribution within the fuel region away from the second neutron modifying material.

2. 发明授权

EP2767981B1 HIGH-TEMPERATURE GAS REACTOR STEAM GENERATOR SYSTEM 有权
标题翻译：蒸汽发生系统用于高温气体反应器
公开(公告)号：EP2767981B1
公开(公告)日：2017-01-18
申请号：EP12839477.2
申请日：2012-10-12
申请人： Mitsubishi Heavy Industries, Ltd.
发明人： MINATSUKI, Isao , MIZOKAMI, Yorikata , OYAMA, Sunao , TSUKAMOTO, Hiroki
IPC分类号： G21D3/08 , G21C1/12 , G21C1/09 , G21C15/253 , G21D1/00 , G21D1/04 , G21C9/00 , G21D3/04 , G21C15/28
CPC分类号： G21C15/18 , F22B35/004 , G21C1/09 , G21C1/10 , G21C1/12 , G21C9/00 , G21C15/253 , G21C15/28 , G21D1/006 , G21D1/04 , G21D3/04 , G21D3/08 , Y02E30/33
摘要： A high temperature gas cooled reactor steam generation system (1) includes a nuclear reactor (2) that has helium gas as a primary coolant and heats the primary coolant by heat generated by a nuclear reaction that decelerates neutrons by a graphite block, a steam generator (3) that has water as a secondary coolant and heats the secondary coolant by the primary coolant via the nuclear reactor (2) to generate steam, a steam turbine (4) that is operated by the steam from the steam generator (3), and a generator (5) that generates electricity according to an operation of the steam turbine (4). Moreover, the system (1) includes pressure adjustment means for setting a pressure of the secondary coolant in the steam generator (3) to be lower than a pressure of the primary coolant in the nuclear reactor (2).

3. 发明公开

EP2946387A1 DISPOSITIF DE CHAUFFAGE D'UN PRESSURISEUR 审中-公开
标题翻译：装置加热的打印HOLDER
公开(公告)号：EP2946387A1
公开(公告)日：2015-11-25
申请号：EP14700496.4
申请日：2014-01-15
申请人： Société Technique pour l'Energie Atomique Technicatome
发明人： ROUX, Jean-Pierre
IPC分类号： G21C1/09 , H05B6/02 , G21D3/08
CPC分类号： G21C1/09 , G21D3/08 , H05B6/10 , H05B6/108 , H05B6/36 , Y02E30/40
摘要： The invention relates to an induction heating device (1) for a pressuriser (2) of a pressurised water nuclear reactor, which pressuriser includes an enclosure (21) having an inner wall made of magnetic material (211), wherein the device comprises at least one heating module (11) having: a winding mounting (111); a winding (112) of conductive wire wound around said mounting (111), said winding (112) generating a magnetic field when an alternating electric current passes therethrough; wherein said device is characterised in that it comprises a module mounting (31) that engages with attachment means for removably attaching said heating module (11) to said module mounting (31), said module mounting (31) being suitable for positioning said heating module outside of the inner wall (211) of the enclosure (21) of said pressuriser (2) in a position that makes it possible to heat said inner wall (211) of the pressuriser (2) by magnetic induction when an electric current passes through said winding (112) of said heating module (11).

4. 发明公开

EP2564393A4 METHOD OF CALIBRATING EXCORE DETECTORS IN A NUCLEAR REACTOR 审中-公开
标题翻译：程序用于校准芯外探测器在核反应堆
公开(公告)号：EP2564393A4
公开(公告)日：2015-03-11
申请号：EP11775431
申请日：2011-04-14
申请人： WESTINGHOUSE ELECTRIC CORP
发明人： KRIEG DAVID JEROME
IPC分类号： G21C17/108 , G21D3/00 , G21D3/08
CPC分类号： G21C17/108 , G21D3/001 , G21D3/08 , Y02E30/40

5. 发明公开

EP2839467A1 EXTENDED OPERATING CYCLE FOR PRESSURIZED WATER REACTOR 无效
标题翻译：加压水反应器的延长操作循环
公开(公告)号：EP2839467A1
公开(公告)日：2015-02-25
申请号：EP13778967.3
申请日：2013-04-17
申请人： Babcock & Wilcox MPower Inc.
发明人： BILOVSKY, Vince, J.
IPC分类号： G21C3/326 , G21C7/04 , G21C7/117
CPC分类号： G21C7/00 , G21C1/322 , G21C3/326 , G21C5/18 , G21C7/04 , G21C7/08 , G21C2003/3262 , G21D3/08 , Y02E30/32 , Y02E30/38 , Y02E30/39
摘要： A pressurized water reactor (PWR) includes a pressure vessel containing a nuclear reactor core immersed in primary coolant water, control rod assemblies (CRA's), and control rod drive mechanisms (CRDM's) operating the CRA's. The reactor core has axially varying 235U enrichment and/or axially varying burnable poison concentration. A CRDM controller controls the CRA's over a burn-up cycle that does not include fuel assembly shuffling and is divided into a plurality of burn-up intervals. The CRDM controller is configured to, for each burn up interval: position the CRA's in accordance with a CRA pattern defining a set of fixed positions for the CRA's except for a sub-set of CRA's designated by the CRA pattern as floating CRA's, and control power level of the PWR by adjusting the floating CRA's without not adjusting the CRA's not designated as floating CRA's. The primary coolant water optionally does not contain soluble neutron poison.
摘要翻译：压水反应堆（PWR）包括容纳浸入一次冷却水中的核反应堆堆芯的压力容器，控制棒组件（CRA's）和操作CRA的控制棒驱动机构（CRDM's）。反应堆堆芯具有轴向变化的235U浓缩和/或轴向变化的可燃中毒浓度。 CRDM控制器通过不包括燃料组件洗牌的燃尽循环来控制CRA，并且被分成多个燃尽间隔。 CRDM控制器被配置为针对每个燃尽间隔：根据CRA模式来定位CRA，CRA模式定义除CRA模式指定的CRA子集之外的CRA的一组固定位置作为浮动CRA，以及控制通过调整浮动CRA而不调整未被指定为浮动CRA的CRA，PWR的功率水平。一次冷却水可选地不含可溶性中子毒物。

6. 发明公开

EP2339590A3 Methods of controlling hydrogen concentrations in an offgas system of a nuclear reactor by passive air injection 有权
标题翻译：通过被动空气喷射控制氢气浓度的在核反应堆的排气系统中的方法
公开(公告)号：EP2339590A3
公开(公告)日：2014-06-18
申请号：EP10195009.5
申请日：2010-12-14
申请人： GE-Hitachi Nuclear Energy Americas LLC
发明人： Shu, Paul Y. , Whittaker, John C. , Gonzaga, Angelito Foz , Tran, Luong C.
IPC分类号： G21D3/04 , G21D3/08 , G21C9/06 , G21C19/317 , B01D53/00
CPC分类号： G21D3/04 , G21C9/06 , G21C19/317 , G21D3/08 , Y02E30/40
摘要： Example embodiments relate to methods of controlling hydrogen concentrations in an offgas system of a nuclear reactor by passive air injection. A method according to a non-limiting embodiment may include passively injecting ambient air through the hydrogen water chemistry system into an existing offgas line of the offgas system. The offgas line is configured to transport non-condensable gases, including hydrogen, from a condenser (102) to a recombiner (104). As a result of the passive air injection, the combined flow of hydrogen and oxygen react in the recombiner (104) to form water vapor, thereby reducing the hydrogen concentration of the offgas exiting the recombiner (104).

7. 发明授权

EP2193524B1 BOILING WATER REACTOR NUCLEAR POWER PLANT WITH ALCOHOL INJECTION 有权
标题翻译：与酒精和注射用沸水堆核电站
公开(公告)号：EP2193524B1
公开(公告)日：2013-05-29
申请号：EP08869404.7
申请日：2008-09-26
申请人： Areva NP Inc.
发明人： STELLWAG, Bernhard , POP, Mihai, G.m.
IPC分类号： G21C17/022 , G21C19/307 , G21D3/08 , C23F11/12
CPC分类号： G21C17/0225 , C02F1/70 , C02F2103/023 , C02F2209/04 , C02F2303/08 , G21C19/307 , G21D3/08 , G21Y2002/103 , G21Y2004/40 , Y02E30/39 , Y02E30/40

8. 发明公开

EP2564393A1 METHOD OF CALIBRATING EXCORE DETECTORS IN A NUCLEAR REACTOR 审中-公开
标题翻译： EEREM KERNREAKTOR的VERFAHREN ZUR KALIBRIERUNG VON EXCORE-DETEKTOREN
公开(公告)号：EP2564393A1
公开(公告)日：2013-03-06
申请号：EP11775431.7
申请日：2011-04-14
申请人： Westinghouse Electric Company LLC
发明人： KRIEG, David, Jerome
IPC分类号： G21C17/108
CPC分类号： G21C17/108 , G21D3/001 , G21D3/08 , Y02E30/40
摘要： A method of calibrating excore detectors for a pressurized water reactor (PWR) (1) includes: measuring peripheral core flux signals using excore detectors (33) disposed at a plurality of locations spaced about the periphery of the core (9), and using the measured power distribution from either a core monitoring system (43) or in-core flux measurement (69). Calibration of the excore detectors (33) is broken into two parts: (1) the relation between the excore detector signal and weighted peripheral assembly axial offset, and (2) the relation between weighted peripheral assembly axial offset and core average axial offset. Relation (2) can be determined by a representative neutronics model. Accuracy of the neutronics solution is improved by applying (83) nodal calibration factors, which represent the ratio of the measured three-dimensional power distribution (75) to the nodal predicted three- dimensional power distribution and correct the neutronic results to match what would be measured if predictive scenarios were actually performed in the actual reactor core (9)·
摘要翻译：用于校准压水反应堆（PWR）的检测器的方法包括：使用设置在围绕芯周边隔开的多个位置处的检测器来测量外围核心磁通信号，并使用来自核心监控系统或核心内磁通测量。探测器的校准分为两部分：（1）探测器信号与加权外围组件轴向偏移之间的关系，（2）加权外围组件轴向偏移与芯轴平均轴向偏移之间的关系。关系（2）可以通过代表性的中子模型来确定。通过应用节点校准因子来提高中子解决方案的准确度，这些因子表示测量的三维功率分布与节点预测的三维功率分布的比值，并校正中子结果以匹配如果预测情景实际上将被测量在实际的反应堆堆芯中进行。

9. 发明公开

EP2048670A1 Methods and devices relating to a nuclear light water reactor of the boiling water kind 有权转让
标题翻译： Verfahren und Vorrichtungen im Zusammenhang mit einem Siedewasseratomreaktortor
公开(公告)号：EP2048670A1
公开(公告)日：2009-04-15
申请号：EP07118186.1
申请日：2007-10-10
申请人： Westinghouse Electric Sweden AB
发明人： Norbäck, Gunilla , Adamsson, Carl
IPC分类号： G21C17/02 , G21D3/04 , G21D3/08
CPC分类号： G21C17/02 , G21D3/001 , G21D3/04 , G21D3/08 , G21Y2002/201 , G21Y2002/204 , G21Y2002/502 , G21Y2004/40 , Y02E30/40
摘要： The present invention concerns a method of determining the R-factor for a bundle of nuclear fuel rods in a nuclear light water reactor of the boiling water reactor kind. The R-factor is a factor that accounts for the weighted local power influence on a fuel rod. A local R-factor ( R i ( z )) is determined for each fuel rod (i) in said bundle and for each of a plurality of levels (z) in an axial direction. The individual axial heat generation profile for a certain fuel rod ( i ) is taken into account when determining the local R-factors ( R i ( z )) for said fuel rod (i). The invention also concerns a processor configured for automatically determining the R-factor, a computer program product, a method of determining the critical power for a bundle of fuel rods, a nuclear energy plant, and a method of operating a nuclear energy plant.
摘要翻译：本发明涉及一种确定沸水反应堆类型的核轻水反应堆中一束核燃料棒的R因子的方法。 R因子是影响加权局部功率对燃料棒影响的因素。对于所述束中的每个燃料棒（i）和沿轴向方向上的多个水平（z）中的每一个确定局部R因子（R i（z））。当确定所述燃料棒（i）的局部R因子（R i（z））时，考虑到某燃料棒（i）的各个轴向发热曲线。本发明还涉及一种配置用于自动确定R因子的处理器，计算机程序产品，确定燃料棒束的关键功率的方法，核能装置以及操作核能装置的方法。

10. 发明授权

EP1374252B1 A NUCLEAR POWER PLANT AND A METHOD OF CONDITIONING ITS POWER GENERATION CIRCUIT 有权
标题翻译：核反应堆系统和方法用于调节电力生成电路
公开(公告)号：EP1374252B1
公开(公告)日：2007-05-02
申请号：EP02718428.2
申请日：2002-03-27
申请人： Pebble Bed Modular Reactor (Proprietary) Limited
发明人： CORREIA, Michael , KRIEL, Willem Adriaan Odendaal
IPC分类号： G21D1/02 , F02C1/05
CPC分类号： G21C1/07 , F02C1/05 , F02C9/18 , F02C9/24 , G21C15/253 , G21D1/02 , G21D3/08 , G21D5/06 , Y02E30/33 , Y02E30/36
摘要： In a nuclear power plant making use of a high temperature gas cooled reactor, it is necessary, prior to commencing power generation and connection of a generator to an electrical distribution grid, to condition the power generation circuit of the plant. This involves creating stable conditions within the power generation circuit. To this end, the plant includes a start-up blower system for circulating working fluid, typically helium, around the power generation circuit until the desired conditions are satisfied. The start-up blower system typically includes a normally open in-line valve, at least one blower connected in parallel with the in-line valve and a normally closed isolation valve connected in series with the blower. Conditioning the power generation circuit will typically include stabilizing the pressure in the circuit at between 10 bar and 50 bar.

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