Molten fuel-salt reactor
    21.
    发明授权
    Molten fuel-salt reactor 失效
    熔融燃料盐反应堆

    公开(公告)号:US4045286A

    公开(公告)日:1977-08-30

    申请号:US642996

    申请日:1975-12-22

    摘要: In a molten-salt reactor, a common vessel contains the reactor core, a neutron-moderating mass pierced by passages for the circulation of the fuel salt, at least one primary heat exchanger which is located close to the reactor core and through which the hot fuel salt passes after discharge from the core, pumps for circulating the cold fuel salt from the heat exchangers back into the reactor core. The free spaces defined within the reactor vessel between the core, the heat exchangers and the pumps except for the passages in which the molten fuel salt is circulated are packed with material which is compatible with the fuel salt.

    摘要翻译: 在熔盐反应器中,公共容器包含反应堆芯,用于燃料盐循环的通道刺穿的中子调节剂,至少一个位于反应堆芯附近的主要热交换器,通过该热交换器将热 燃料盐从核心排出后通过,用于将冷燃料盐从热交换器循环回到反应堆堆芯中。 在核心,热交换器和除了熔融燃料盐循环的通道之外的反应器容器内限定的自由空间用与燃料盐相容的材料填充。

    DRILLHOLE NUCLEAR REACTOR
    22.
    发明公开

    公开(公告)号:US20240339231A1

    公开(公告)日:2024-10-10

    申请号:US18744364

    申请日:2024-06-14

    摘要: A nuclear reactor system includes a first drillhole extending from a terranean surface through one or more subterranean formations; a reactor core positioned in the first drillhole, and including at least one nuclear fuel element; a second drillhole extending from the terranean surface through the one or more subterranean formations and separated from the first drillhole by a portion of a rock formation; a heat exchanger positioned in the second drillhole in thermal communication with the reactor core through the portion of the rock formation; and a coolant system thermally coupled to the heat exchanger and configured to transport a fluid coolant between the heat exchanger and the terranean surface.

    SYSTEMS AND METHODS FOR ELECTROCHEMICAL EXTRACTION OF REDUCED FISSION PRODUCTS FROM IRRADIATED MOLTEN SALT COMPOSITIONS

    公开(公告)号:US20240312656A1

    公开(公告)日:2024-09-19

    申请号:US18604025

    申请日:2024-03-13

    IPC分类号: G21C19/31 G21C3/54

    CPC分类号: G21C19/31 G21C3/54

    摘要: Fission of uranium-235 produces a wide range of fission products. Of particular importance is the production of molybdenum-99 due to its uses in the medical field. Fission products can be extracted from a molten salt reactor through electrochemical deposition by utilizing an electrode submerged in the flow of irradiated molten salt. However, this is likely to disrupt the redox of the irradiated molten fuel leading to harmful corrosion of the reactor. The present invention utilizes three electrode sets to capture fission products from irradiated molten salt of a molten salt reactor, monitor the redox behavior of the irradiated molten salt, and maintaining the balance of uranium ions to avoid harmful corrosion to the reactor's core.