CURVILINEAR ELECTROMAGNETIC PUMP
    1.
    发明申请

    公开(公告)号:WO2022039792A1

    公开(公告)日:2022-02-24

    申请号:PCT/US2021/025477

    申请日:2021-04-01

    Abstract: A curvilinear electromagnetic pump is configured to follow a curve, such as by coupling multiple linear pump segments together that are offset by an angle with respect to each other. The curvilinear electromagnetic pump can curve within two dimensions, or within three dimensions. The curvilinear electromagnetic pump allows for more efficient arrangement of components and systems within a nuclear reactor vessel and allows a significantly reduced reactor vessel height as compared to a linear pump arranged vertically. The curvilinear electromagnetic pump may follow the curvature of the reactor vessel wall and may be entirely disposed near the bottom of the reactor vessel.

    CARTRIDGE CORE BARREL FOR NUCLEAR REACTOR
    2.
    发明申请

    公开(公告)号:WO2022039790A1

    公开(公告)日:2022-02-24

    申请号:PCT/US2021/022017

    申请日:2021-03-11

    Abstract: A nuclear reactor is designed to couple the load path of the control elements with the reactor core, thus reducing the opportunity for differential movement between the control elements and the reactor core. A cartridge core barrel can be fabricated in a manufacturing facility to include the reactor core, control element supports, and control element drive system. The cartridge core barrel can be mounted to a reactor vessel head, and any movement, such as through seismic forces, transmits an equal direction and magnitude to the control elements and the reactor core, thus inhibiting the opportunity for differential movement.

    SODIUM VAPORIZER AND METHOD FOR USE OF SODIUM VAPORIZER

    公开(公告)号:WO2021040911A1

    公开(公告)日:2021-03-04

    申请号:PCT/US2020/042905

    申请日:2020-07-21

    Abstract: A vaporizer includes an outer tube configured to receive a flow of heated gas and an inner tube disposed at least partially within the outer tube. The inner tube is spaced apart from the outer tube such that the flow of heated gas is channeled through an annular space therebetween. The vaporizer also includes a crucible disposed at least partially within the inner tube. The crucible is extendable and retractable relative to the inner tube and within the outer tube. The crucible is configured to hold a molten metal such that a surface area of the molten metal exposed to the flow of heated gas is adjustable based on the position of the crucible relative to the inner tube. A heater is configured to vaporize the molten material and the vapor mixes with the flow of heated gas.

    REFLECTORS FOR MOLTEN CHLORIDE FAST REACTORS

    公开(公告)号:WO2019226218A2

    公开(公告)日:2019-11-28

    申请号:PCT/US2019/021791

    申请日:2019-03-12

    Abstract: A reflector assembly for a molten chloride fast reactor (MCFR) includes a support structure with a substantially cylindrical base plate, a substantially cylindrical top plate, and a plurality of circumferentially spaced ribs extending between the base plate and the top plate. The support structure is configured to encapsulate a reactor core for containing nuclear fuel. The MCFR also includes a plurality of tube members disposed within the support structure and extending axially between the top plate and the bottom plate. The plurality of tube members are configured to hold at least one reflector material to reflect fission born neutrons back to a center of the reactor core.

    GAS-COOLED PRESSURE TUBE REACTOR
    5.
    发明申请

    公开(公告)号:WO2018204857A2

    公开(公告)日:2018-11-08

    申请号:PCT/US2018/031208

    申请日:2018-05-04

    Abstract: A gas-cooled pressure tube nuclear reactor is described that uses a room temperature and pressure gas as a primary coolant and a liquid moderator as a secondary coolant. The primary coolant, which may be maintained in a supercritical state, is circulated through fuel columns in a pool of the liquid moderator. The primary coolant removes the heat generated by fission from the nuclear fuel. The heated primary coolant is then passed to one or more turbines to generate power. The primary coolant is then repressurized by one or more compressors using some of the generated power from the turbines. Several modified Brayton cycle configurations are described that are uniquely suited to the operating conditions of the gas-cooled pressure tube reactor.

    METHOD AND SYSTEM FOR RECYCLING PYROLYSIS TAIL GAS THROUGH CONVERSION INTO FORMIC ACID

    公开(公告)号:WO2018176026A1

    公开(公告)日:2018-09-27

    申请号:PCT/US2018/024289

    申请日:2018-03-26

    Abstract: This disclosure describes systems and methods for using pyrolysis tail gas as the source for additional hydrogen to be used in the pyrolysis reaction. Tail gas is separated from the pyrolysis products and a portion of the tail gas is converted into formic acid (HCOOH). The formic acid is then injected into the pyrolysis reactor where it becomes the donor of two monohydrogen atoms and is ultimately converted into CO2 under reaction conditions. In this fashion, a closed loop pyrolysis hydrogen donor system may be created utilizing a generally non-toxic intermediary derived from the pyrolysis reaction products. This disclosure also describes using a ruthenium catalyst supported on particles of activated carbon to improve the yield of pyrolysis reactions.

    SYSTEM AND METHOD FOR MODELING A NUCLEAR REACTOR

    公开(公告)号:WO2018157157A3

    公开(公告)日:2018-08-30

    申请号:PCT/US2018/020027

    申请日:2018-02-27

    Abstract: A system is provided that determines optimal movements of fuel assemblies in a nuclear reactor, such as a traveling wave reactor (TWR). Such a system may be capable of modeling core operations and fuel moves in parallel to determine optimal fuel cycle moves responsive to one or more constraints, including, but not limited to core criticality and location of a deflagration wave within an operating reactor core. According to one embodiment, the optimal solution may be determined using a branch search to simulate possible fuel moves.

    ELECTRO-SYNTHESIS OF URANIUM CHLORIDE FUEL SALTS
    8.
    发明申请
    ELECTRO-SYNTHESIS OF URANIUM CHLORIDE FUEL SALTS 审中-公开
    电解合成氯化铀燃料盐

    公开(公告)号:WO2018031681A1

    公开(公告)日:2018-02-15

    申请号:PCT/US2017/046139

    申请日:2017-08-09

    Abstract: This disclosure describes systems and methods for synthesizing UCI 3 from UCI 4 . These systems and methods may also be used to directly synthesize binary and ternary embodiments of uranium salts of chloride usable as nuclear fuel in certain molten salt reactor designs. The systems and methods described herein are capable of synthesizing any desired uranium chloride fuel salt that is a combination of UCI 4 , UCI 3 and one or more non-fissile chloride compounds, such as NaCl. In particular, the systems and methods described herein are capable of synthesizing any UCI 3 -UCI 4 -NaCl or UCI 3 -NaCl fuel salt composition from UCI 4 -NaCl.

    Abstract translation: 本公开描述了用于从UCI 4 合成UCI <3>的系统和方法。 这些系统和方法也可以用于直接合成在某些熔盐反应器设计中可用作核燃料的氯化铀盐的二元和三元实施方案。 本文所述的系统和方法能够合成任何所需的UCl 4,UCl 3和一种或多种非易裂变氯化物化合物的组合的氯化铀燃料盐, 如NaCl。 具体而言,本文所述的系统和方法能够合成任何UCl 3 -UCl 4 -NaCl或UCl 3 -NaCl燃料盐组合物 来自UCI 4 -NaCl。

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