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    NUCLEAR REACTOR SUPPORT AND SEISMIC RESTRAINT WITH IN-VESSEL CORE RETENTION COOLING FEATURES
    1.
    发明申请
    NUCLEAR REACTOR SUPPORT AND SEISMIC RESTRAINT WITH IN-VESSEL CORE RETENTION COOLING FEATURES 审中-公开
    核反应堆支持和地下储存与内部维持冷却特性

    公开(公告)号：WO2015191441A1

    公开(公告)日：2015-12-17

    申请号：PCT/US2015/034659

    申请日：2015-06-08

    Applicant: BABCOCK & WILCOX MPOWER, INC.

    Inventor： EDWARDS, Tyler A. ,  EDWARDS, Michael J.

    IPC: G21C5/12

    CPC classification number: G21C5/10 ,  G21C9/016 ,  G21C13/024 ,  G21C15/18 ,  Y02E30/40

    Abstract: A nuclear island includes a nuclear reactor, a lateral seismic restraint, and an in-vessel reactor core retention cooling system. The lateral seismic restraint includes a vertically oriented pin attached to one of the bottom of the lower vessel head and the floor underneath the nuclear reactor, and a mating pin socket is attached to the other of the bottom of the lower vessel head and the floor. The in-vessel reactor core retention cooling system includes one or more baffles, optionally thermally insulating material, disposed alongside the exterior surface of a lower portion of the reactor pressure vessel including at least the lower vessel head. A plenum is defined between the one or more baffles and the exterior surface of a lower portion of the reactor pressure vessel. The one or more baffles may define a lower plenum inlet surrounding the lateral seismic restraint.

    Abstract translation: 核岛包括核反应堆，横向地震约束和容器内反应堆堆芯保持冷却系统。 横向地震抑制装置包括一个垂直定向的销钉，该销钉连接到下部船舶头部的底部和核反应堆底部之间的一个底部，并且配合销座连接到下部船只头部和底部的另一个底部。 容器内反应堆堆芯保持冷却系统包括一个或多个挡板，任选的隔热材料，沿着反应堆压力容器的下部的外部表面设置，至少包括下部容器头部。 在一个或多个挡板和反应堆压力容器的下部的外表面之间限定增压室。 一个或多个挡板可以限定围绕横向地震约束的下部增压室入口。

    METHOD OF COOLING NUCLEAR REACTOR AND NUCLEAR REACTOR INCLUDING POLYHEDRAL BORON HYDRIDE OR CARBORANE ANIONS
    2.
    发明申请
    METHOD OF COOLING NUCLEAR REACTOR AND NUCLEAR REACTOR INCLUDING POLYHEDRAL BORON HYDRIDE OR CARBORANE ANIONS 审中-公开
    冷却核反应堆和核反应堆的方法，包括聚合硼氢化物或碳氢化合物

    公开(公告)号：WO2014197076A2

    公开(公告)日：2014-12-11

    申请号：PCT/US2014/027162

    申请日：2014-03-14

    Applicant: CERADYNE, INC.

    Inventor： COOK, Kevin S. ,  BOSLEY, Beth D.

    IPC: G21C5/12

    CPC classification number: G21C15/28 ,  G21C5/12 ,  G21C5/123 ,  G21C9/033 ,  G21C13/00 ,  G21C15/18 ,  Y02E30/40

    Abstract: A method of cooling a nuclear reactor core is disclosed. The method includes contacting the nuclear reactor core with an aqueous solution comprising at least one of polyhedral boron hydride anions or carborane anions. Nuclear reactors are also disclosed. The nuclear reactor has a neutron moderator that is an aqueous solution comprising at least one of polyhedral boron hydride anions or carborane anions, or the nuclear reactor has an emergency core cooling system including a vessel containing a volume of an aqueous solution comprising at least one of polyhedral boron hydride anions or carborane anions. The nuclear reactor can also have both an aqueous solution comprising at least one of polyhedral boron hydride anions or carborane anions as a neutron moderator and an emergency core cooling system that includes an aqueous solution comprising at least one of polyhedral boron hydride anions or carborane anions.

    Abstract translation: 公开了一种冷却核反应堆堆芯的方法。 该方法包括使核反应堆芯与包含多面体硼氢化物阴离子或碳硼烷阴离子中的至少一种的水溶液接触。 核反应堆也被披露。 核反应堆具有中子减速剂，其是包含多面体硼氢化物阴离子或碳硼烷阴离子中的至少一种的水溶液，或者核反应堆具有应急芯冷却系统，其包括含有一定体积的水溶液的容器，该容器包含至少一种 多面体硼氢化物阴离子或碳硼烷阴离子。 核反应堆还可以具有包含多面体硼氢化物阴离子或碳硼烷阴离子中的至少一种作为中子缓和剂的水溶液和包括含有多面体硼氢化物阴离子或碳硼烷阴离子中的至少一种的水溶液的应急芯冷却系统。

    COEUR DE REACTEUR A NEUTRONS RAPIDES DE CONFIGURATION PERFECTIONNEE.
    3.
    发明申请
    COEUR DE REACTEUR A NEUTRONS RAPIDES DE CONFIGURATION PERFECTIONNEE. 审中-公开
    具有改进配置的快中子反应堆芯

    公开(公告)号：WO2011154669A2

    公开(公告)日：2011-12-15

    申请号：PCT/FR2011/051336

    申请日：2011-06-10

    Applicant: ELECTRICITE DE FRANCE ,  COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES ,  MASSARA, Simone ,  TETART, Philippe ,  SCHMITT, Damien ,  JOURDHEUIL, Thomas

    Inventor： MASSARA, Simone ,  TETART, Philippe ,  SCHMITT, Damien ,  JOURDHEUIL, Thomas

    IPC: G21C1/02 ,  G21C5/18 ,  G21C5/20 ,  G21C5/12 ,  G21C5/16

    CPC classification number: G21C1/024 ,  G21C5/18 ,  G21C5/20 ,  Y02E30/34

    Abstract: La présente invention concerne une configuration de cœur de réacteur à neutrons rapides, refroidi par un métal liquide. Le cœur comporte un ensemble d'éléments combustibles comprenant un matériau fertile et/ou un matériau fissile, l'ensemble de tels éléments combustibles étant agencé selon une forme générale de cylindre. Au sens de l'invention, un premier ensemble d'éléments combustibles (Cl, C2, C3), disposé selon une couronne en périphérie du cylindre, comporte relativement plus de matériau fissile qu'un deuxième ensemble d'éléments combustibles (FERT), disposé au centre du cylindre. Un tel agencement permet avantageusement de réduire un effet de vidange du métal liquide et de là, d'améliorer la sécurité du réacteur.

    Abstract translation: 本发明涉及液态金属冷却的快中子反应堆核心的结构。 核心包括燃料元件的组合件，其包括肥沃材料和/或可裂变材料，这种燃料元件的组件以气缸的一般形式布置。 在本发明的上下文中，燃料元件（C1，C2，C3）围绕圆柱体的周边布置成环的第一组件包括比燃料元件（FERT）的第二组件相对更易裂变的材料，其是 放置在圆筒的中心。 这样的配置有利于使液体金属排放效果降低，从而提高反应器的安全性。

    A NUCLEAR REACTOR
    4.
    发明申请
    A NUCLEAR REACTOR 审中-公开
    核反应堆

    公开(公告)号：WO2004102585A3

    公开(公告)日：2005-02-10

    申请号：PCT/IB2004001538

    申请日：2004-05-14

    Applicant: PEBBLE BED MODULAR REACTOR PTY ,  VORSTER JOHANN ,  HORNISCHER EDGAR

    Inventor： VORSTER JOHANN ,  HORNISCHER EDGAR

    IPC: G21C1/07 ,  G21C5/12 ,  G21C5/14

    CPC classification number: G21C1/07 ,  G21C5/126 ,  G21C5/14 ,  G21C11/06 ,  G21Y2002/303 ,  G21Y2002/304 ,  G21Y2004/30 ,  Y02E30/36

    Abstract: This invention relates to a nuclear reactor 10 which includes a hollow core vessel 12 and a modular filler member 20 positioned within the core vessel 12 such that a core cavity 22 is defined around the filler member 20. The filler member 20 is of layered structure comprising a plurality of interconnected layers 42 of blocks 40, each layer 42 comprising a plurality of laterally inter-engaged blocks 40. The invention extends to a method of constructing a central column 20 of a nuclear reactor 10.

    Abstract translation: 本发明涉及一种核反应堆10，其包括中空的核心容器12和位于核心容器12内的模块化填料构件20，使得芯腔22围绕填料构件20被限定。填料构件20是分层结构，包括 块40的多个互连层42，每个层42包括多个横向相互接合的块40。本发明延伸到构造核反应堆10的中心柱20的方法。

    DEVICE FOR RECOVERY OF ENERGY FROM SPENT FUEL OF NUCLEAR REACTORS AND PROCESS FOR ENERGY RECOVERY FROM SPENT FUEL OF NUCLEAR REACTORS
    6.
    发明申请
    DEVICE FOR RECOVERY OF ENERGY FROM SPENT FUEL OF NUCLEAR REACTORS AND PROCESS FOR ENERGY RECOVERY FROM SPENT FUEL OF NUCLEAR REACTORS 审中-公开

    公开(公告)号：WO2021170157A1

    公开(公告)日：2021-09-02

    申请号：PCT/CZ2021/050020

    申请日：2021-02-17

    Applicant: SKODA, Radek

    Inventor： SKODA, Radek

    IPC: G21C1/06 ,  G21C5/12 ,  G21C19/48

    Abstract: Due to the parasitic absorption of neutrons on fission debris, in VVER-, BWR-, and PWR-type nuclear reactors, fuel is nowadays removed from the reactor, although the fuel still contains some usable material. This material is further utilized with the release of energy in the device described in the invention. In the device for recovery of energy from spent fuel of nuclear reactors, already irradiated fuel assemblies are used in other geometries, using different physical parameters and materials than in the original reactors. In particular, the fuel is operated at maximum fuel temperature lower than in the reactor in which it was originally irradiated, at a temperature at least 150 C lower than in the case of fuel from a VVER reactor, 160 C lower than in the case of fuel from a BWR reactor, and 140 C lower than in the case of fuel from a PWR reactor. The moderator in this device has lower absorption in the fuel than in the reactor in which it was originally irradiated, at least 5% lower in the case of fuel from a VVER reactor, at least 5% lower in the case of fuel from a BWR reactor, and at least 7% lower in the case of spent fuel of a PWR reactor. The coolant of the device for recovery of energy from spent fuel of VVER nuclear reactors is at a pressure lower than 12 MPa, in the case of spent fuel of BWR reactors, it is at a pressure lower than 6.5 MPa, and in the case of spent fuel of PWR reactors, it is at a pressure lower than 15 MPa. The spacing between the centers of some of the fuel assemblies of the device for recovery of energy from spent fuel of nuclear reactors is larger than in the reactor in which the fuel was originally irradiated, 3 mm larger in the case of fuel from a VVER reactor, 2 mm larger in the case of fuel from a BWR reactor, and 3 mm larger in the case of fuel from a PWR reactor. The device for recovery of energy from spent fuel of nuclear reactors is primarily designed for the heating industry and can be used also with non-irradiated fuel.

    PASSIVE REACTIVITY CONTROL OF NUCLEAR THERMAL PROPULSION REACTORS
    7.
    发明申请
    PASSIVE REACTIVITY CONTROL OF NUCLEAR THERMAL PROPULSION REACTORS 审中-公开

    公开(公告)号：WO2017222614A3

    公开(公告)日：2017-12-28

    申请号：PCT/US2017/022165

    申请日：2017-03-13

    Applicant: ULTRA SAFE NUCLEAR CORPORATION

    Inventor： VENNERI, Paolo, Francesco ,  EADES, Michael, John

    IPC: G21C3/326 ,  G21C5/12 ,  G21C7/04 ,  G21D5/02

    Abstract: Passive reactivity control technologies that enable reactivity control of a nuclear thermal propulsion (NTP) system with little to no active mechanical movement of circumferential control drums. By minimizing or eliminating the need for mechanical movement of the circumferential control drums during an NTP burn, the reactivity control technologies simplify controlling an NTP reactor and increase the overall performance of the NTP system. The reactivity control technologies mitigate and counteract the effects of xenon, the dominant fission product contributing to reactivity transients. Examples of reactivity control technologies include, employing burnable neutron poisons, tuning hydrogen pressure, adjusting wait time between burn cycles or merging burn cycles, and enhancement of temperature feedback mechanisms. The reactivity control technologies are applicable to low-enriched uranium NTP systems, including graphite composite fueled and tungsten ceramic and metal matrix (CERMET), or any moderated NTP system, such as highly- enriched uranium graphite composite NTP systems.

    중수로의 핵연료 절감 방법
    10.
    发明申请
    중수로의 핵연료 절감 방법 审中-公开

    公开(公告)号：WO2019107733A1

    公开(公告)日：2019-06-06

    申请号：PCT/KR2018/011878

    申请日：2018-10-10

    Applicant: 한국수력원자력 주식회사

    Inventor： 김성민 ,  고성욱 ,  김영애 ,  박동환 ,  류의승 ,  유성창 ,  김용배

    IPC: G21C7/26 ,  G21C5/12 ,  C22C19/07

    Abstract: 본 발명은 특히 불필요한 출력감발을 조절봉 소재 변경으로 억제시킴과 동시에 코발트-60을 생산할 수 있는 핵연료 절감 방법에 관한 것으로서, 제1 내지 제7 조절봉 군으로 이루어지는 7개의 조절봉 군을 각각 핵연료집합체의 서로 다른 부위에 인입 또는 인출 가능하게 설치하되, 제7 조절봉 군은 제7 조절봉 군을 이루는 조절봉들의 반응도 값을 나머지 조절봉 군을 이루는 조절봉들의 반응도 값 보다 작게 제작하는 제1단계; 및, 제1 내지 제7 조절봉 군을 모두 핵연료집합체에서 인출시킬 때, 제7 조절봉 군을 가장 마지막으로 인출시키는 제2단계;로 이루어짐으로써, 제7 조절봉 군의 인출 과정에서 액체영역제어계통(LZC, Liquid Zone Control system)의 수위가 자동으로 조절봉 인입조건 수위 이상으로 상승됨으로 인한 제7 조절봉 군의 자동 재인입 현상을 방지하여, 제7 조절봉 군의 자동 재인입으로 인한 불필요한 연소도 억제 현상을 해소시킴으로써, 연소도를 상승시켜 소요되는 핵연료를 대폭 절감시킬 수 있는 중수로의 핵연료 절감 방법을 제공하고자 한다.

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