A LOW PRESSURE WATER REACTOR AND A METHOD FOR CONTROLLING A LOW PRESSURE WATER REACTOR

    公开(公告)号:WO2023012140A1

    公开(公告)日:2023-02-09

    申请号:PCT/EP2022/071630

    申请日:2022-08-02

    Abstract: A low pressure water reactor (LPWR) and a method for controlling a LPWR are proposed. The LPWR comprises a reactor vessel with an internal cavity comprising a primary coolant, a riser tube, and a core located below ground level with 6-15 bars atmosphere pressure; a steam drum connected to the riser tube and located at ground level at a pressure of 1 -10 bars absolute; a water storage tank to store borated water; a passive injection system to inject the borated water from the water storage tank into the vessel; and low pressure steam turbines to generate power at a pressure of 1-10 bars atmosphere. The vessel heats water up to a certain temperature and the riser tube converts the heated water to steam, which is further delivered to the turbine(s). The conversion creates a difference in a primary coolant density that initiates a density-driven natural circulation of the primary coolant in the riser tube, downcomer, steam drum and core.

    INTEGRATED SYSTEM FOR CONVERTING NUCLEAR ENERGY INTO ELECTRICAL, MECHANICAL, AND THERMAL ENERGY

    公开(公告)号:WO2022245568A2

    公开(公告)日:2022-11-24

    申请号:PCT/US2022/028312

    申请日:2022-05-09

    Applicant: NUGEN, LLC

    Abstract: Provided is an apparatus for generating electricity comprising a gas propellant chamber, a containment vessel, and a rotor/stator assembly partially integrated within the containment vessel. The gas propellant chamber is disposed within the containment vessel and comprises a compressor, a nuclear fuel chamber, and a turbine assembly, wherein a drive shaft extending axially through the gas propellant chamber couples the compressor to the turbine assembly. The rotor of the rotor/stator assembly is disposed internally of the containment vessel and is in communication with the stator, the stator being disposed externally of the containment vessel. The apparatus thereby provides a simpler and safer design that is both scalable and adaptable. The apparatus is easily and safely transportable and can be designed to be highly nuclear-proliferation-resistant.

    NUCLEAR REACTOR SYSTEM WITH LIFT-OUT CORE ASSEMBLY

    公开(公告)号:WO2022035871A2

    公开(公告)日:2022-02-17

    申请号:PCT/US2021/045401

    申请日:2021-08-10

    Abstract: A modular nuclear reactor system includes a lift-out, replaceable nuclear reactor core configured for replacement as a singular unit during a single lift-out event, such as rather than lifting and replacing individual fuel assemblies and/ or fuel elements. The system includes a reactor vessel and a power generation system configured to convert thermal energy in a high temperature working fluid received from the reactor vessel into electrical energy. The reactor vessel includes: a vessel inlet and an adjacent vessel outlet arranged near a bottom on the vessel; a vessel receptacle configured to receive a unified core assembly; locating datums in the base of the vessel receptacle and configured to constrain a core assembly in multiple degrees of freedom; and an interstitial zone surrounding the vessel receptacle and housing a set of control or moderating drums.

    PASSIVE VENTING ARRANGEMENT OF STOICHIOMETRIC HYDROGEN PLUS OXYGEN GASES GENERATED IN A SHIELDED CONTAINER

    公开(公告)号:WO2020236823A1

    公开(公告)日:2020-11-26

    申请号:PCT/US2020/033613

    申请日:2020-05-19

    Abstract: A passive venting arrangement for use in venting of gases produced by radioactive materials includes a source gas region for receiving the gases produced by the radioactive materials; a filter ullage region disposed above the source gas region and segregated therefrom except for a plurality of bore holes which each extend between, and fluidly couple, the source gas region and the filter ullage region; and a plurality of filters disposed in contact with the filter ullage region, wherein each filter is structured to provide for the exchange of gases from the filter ullage region through the filter to an ambient environment.

    COMPACT RAISED FACE FLANGE
    6.
    发明申请

    公开(公告)号:WO2020068144A1

    公开(公告)日:2020-04-02

    申请号:PCT/US2018/065791

    申请日:2018-12-14

    Inventor: LISZKAI, Tamas

    Abstract: A raised face flange assembly comprises an upper flange (11) to couple to a lower flange (12) using one or more bolts (5): wherein the upper flange (11) or the lower flange (12) comprises: a bolting face (25) defining one or more openings for the one or more bolts (5), respectively; a pair of raised faces (21, 22) including a first raised face and a second raised face to make contact with a mating surface of the other of the upper flange (11) or the lower flange (12); wherein a distance between an area of the second raised face (22) and a plane corresponding to the bolting face (25) is greater than a distance between an area of the first raised face (21) and the plane to distribute contact force with a mating surface over the area of the second raised face (22) to maintain a seal.

    原子炉支持構造
    8.
    发明申请
    原子炉支持構造 审中-公开
    反应堆支撑结构

    公开(公告)号:WO2017064869A1

    公开(公告)日:2017-04-20

    申请号:PCT/JP2016/004582

    申请日:2016-10-14

    Applicant: 藤田 琢己

    Inventor: 藤田 琢己

    CPC classification number: G21C13/02 G21C13/024 Y02E30/40

    Abstract: 【課題】 従来の免震原子炉構造は、シリンダ状の容器とピストン状の円筒からなるダンパーを用いているために、大きな横揺れが生じるとダンパーが損傷または破壊し、原子炉の十分な免震機能が維持できなくなるという問題があった。 【解決手段】 本発明は、逆U字型形状体22により原子炉5を吊持しているので、地震の横揺れが生じた場合でも、原子炉5は逆U字型形状体22の支点部22aを中心に原子炉収納部21を略横方向に揺動するだけで、原子炉5に何ら衝撃が生じることなく、また、地震の縦揺れが生じた場合には、逆U字型形状体22の支点部22a下部の原子炉収納部21の横断面形状より大きい形状からなる弾性構造体23の大きな弾性力により縦方向の揺れが吸収されるので、原子炉5に衝撃が生じることなく、原子炉5の放射性物質の漏れを有効に防止することができる。

    Abstract translation:

    常规的地震隔离器的结构,由于使用阻尼器,包括具有活塞形筒状的圆筒状的容器的,大时,会发生辊阻尼器损坏或破坏 并且存在无法维持核反应堆的充分隔震功能的问题。 解决方案:在本发明中,由于核反应堆5悬挂在倒U形体22上,所以即使当地震滚动时,核反应堆5也由倒U形体22的支点支撑 仅通过使核反应堆5的核心部22a的横向的反应堆收容部21摇动,在地震的纵向振动的情况下不会产生冲击, 由于抖动的纵向方向被由大的形状比主体22的反应器壳体部21的支撑部22a底部的横截面形状的弹性结构23的大的弹性力吸收,无冲击在反应器5中产生 能够有效地防止核反应堆5的放射性物质泄漏。

    CONVECTIVE DRY FILTERED CONTAINMENT VENTING SYSTEM
    9.
    发明申请
    CONVECTIVE DRY FILTERED CONTAINMENT VENTING SYSTEM 审中-公开
    对流干燥过滤式容器通风系统

    公开(公告)号:WO2016011055A3

    公开(公告)日:2016-03-10

    申请号:PCT/US2015040413

    申请日:2015-07-14

    Applicant: AREVA INC

    CPC classification number: G21C13/022 G21C9/004 G21C19/303 G21F9/02 Y02E30/40

    Abstract: A dry FCVS for a nuclear reactor containment is provided. The dry FCVS includes a housing and a round and/or elongated aerosol filter inside the housing for removing contaminant aerosols from gas passing through the housing during venting of the containment. The housing includes at least one inlet portion configured for directing gas into the aerosol filter during the venting of the containment and an outlet portion for gas filtered by the aerosol filter during the venting of the containment. The dry filtered containment venting system is arranged and configured such that when a flow of gas through the outlet portion is closed off at least one of convective, radiant and conductive heat transfer removes decay heat of aerosols captured in the aerosol filter.

    Abstract translation: 提供了用于核反应堆安全壳的干燥FCVS。 干燥的FCVS包括壳体和在壳体内部的圆形和/或细长的气溶胶过滤器,用于在通气过程中去除通过壳体的气体中的污染物气溶胶。 该壳体包括至少一个入口部分,该入口部分被配置用于在安全壳的排气期间将气体引导到气雾过滤器中,以及用于在安全壳的排气期间由气溶胶过滤器过滤的气体的出口部分。 经过干燥过滤的安全壳通风系统被设置和构造成使得当通过出口部分的气体流被关闭时,对流,辐射和传导性热传递中的至少一个去除在气溶胶过滤器中捕获的气溶胶的衰变热。

    NUCLEAR REACTOR SAFETY SYSTEM
    10.
    发明申请
    NUCLEAR REACTOR SAFETY SYSTEM 审中-公开
    核反应堆安全系统

    公开(公告)号:WO2015089662A1

    公开(公告)日:2015-06-25

    申请号:PCT/CA2014/051224

    申请日:2014-12-17

    Applicant: HATCH LTD.

    Abstract: A nuclear reactor system is disclosed which provides an auxiliary cooling system and improved safety in the event of corrosion failure. The reactor comprises an inner reactor vessel containing a reactor core and a liquid fuel, and an outer containment vessel, with an intermediate space between the vessels being filled with a protective material. The protective material is at least partly in a solid state during normal operation of the reactor, and is liquefied by increasing temperatures within the reactor vessel due to abnormal operating conditions and provides enhanced cooling in the liquid state. The protective material and/or the coolant of a heat exchanger may dilute the liquid fuel during corrosive failure, and may optionally be provided with neutron absorbing material to prevent a fission chain reaction from occurring outside the reactor vessel.

    Abstract translation: 公开了一种核反应堆系统,其提供辅助冷却系统并且在腐蚀失效的情况下提高安全性。 反应器包括含有反应堆芯和液体燃料的内部反应器容器和外部容纳容器,容器之间的中间空间填充有保护材料。 保护材料在反应器的正常操作期间至少部分处于固态,并且由于异常操作条件而在反应器容器内由于升高的温度而被液化,并且在液体状态下提供增强的冷却。 热交换器的保护材料和/或冷却剂可能在腐蚀性破坏期间稀释液体燃料,并且可任选地设置中子吸收材料,以防止裂变链反应发生在反应器容器外部。

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