Detectors, systems, and methods for continuously monitoring neutrons with enhanced sensitivity

    公开(公告)号:US11715577B2

    公开(公告)日:2023-08-01

    申请号:US17191324

    申请日:2021-03-03

    发明人: Michael D. Heibel

    IPC分类号: G21G1/08 G01T3/00 G21C17/00

    CPC分类号: G21G1/08 G01T3/00 G21C17/00

    摘要: A neutron detector is disclosed herein. The neutron detector can include a housing defining a cavity, wherein the housing is configured to permit an amount of neutrons emitted from a core of a nuclear reactor to enter the cavity. The neutron detector can also include an amount of a neutron sensitive material dispositioned within the cavity, wherein the neutron sensitive material is configured to generate and emit gamma rays upon interacting with the amount of neutrons. The neutron detector can further include an amount of electron emissive material configured to generate and emit a current of electrons upon interacting with the emitted gamma rays, wherein the current of electrons is indicative of the amount of neutrons emitted from the core of the nuclear reactor.

    Methods of energy generation from a thorium molten salt system

    公开(公告)号:US11621098B2

    公开(公告)日:2023-04-04

    申请号:US17444483

    申请日:2021-08-05

    申请人: Texas Thorium LLC

    摘要: A method of generating power using a Thorium-containing molten salt fuel is disclosed. One example includes the steps of providing a vessel containing a molten salt fuel, generating a proton beam externally to the vessel, where the externally generated proton beam is of an energy level sufficient to interact with material within a fuel rod in the vessel to produce (p, n) reactions resulting in the generation of neutrons at a first energy level. Neutrons generated within the vessel through the (p, n) reactions are utilized to produce a fission reaction which increases the heat content of the molten salt within the vessel. In the example, a heat exchanger is used to extract heat from the molten salt within the vessel and power is generated from the extracted heat.

    TARGETRY COUPLED SEPARATIONS
    3.
    发明申请

    公开(公告)号:US20220310281A1

    公开(公告)日:2022-09-29

    申请号:US17533264

    申请日:2021-11-23

    申请人: TerraPower, LLC

    摘要: Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art.

    Targetry coupled separations
    4.
    发明授权

    公开(公告)号:US10141079B2

    公开(公告)日:2018-11-27

    申请号:US14757683

    申请日:2015-12-23

    申请人: TerraPower, LLC

    摘要: Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art.

    System For Active Long Range Detection And Identification Of Special Nuclear Materials Using A High Intensity Particle Beam
    6.
    发明申请
    System For Active Long Range Detection And Identification Of Special Nuclear Materials Using A High Intensity Particle Beam 审中-公开
    使用高强度粒子束主动长距离检测和识别特殊核材料的系统

    公开(公告)号:US20160187270A1

    公开(公告)日:2016-06-30

    申请号:US15015346

    申请日:2016-02-04

    IPC分类号: G01N23/222 G21G1/08

    CPC分类号: G01N23/222 G21G1/08

    摘要: A long-range method and a system for reliably detecting and identifying special nuclear materials is provided that relies on the emission of delayed neutrons present in the decay of fission products (delayed neutron precursors) as a unique signature for the special nuclear materials, such as highly enriched uranium (235/238U). The method relies on a time-of-flight measurement in the first 1 μs after the inducing radiation pulse, and pulse height data analysis for both neutrons and gamma rays that can be done at a much higher data rate than in traditional pulse processing systems. The thermal neutron fission within the time regime of 100-500 μs provides a unique signature of special nuclear materials such as the highly enriched uranium.

    摘要翻译: 提供了一种远程方法和可靠地检测和识别特殊核材料的系统,其依赖于存在于裂变产物(延迟中子前体)衰变中的延迟中子的排放作为特殊核材料的独特签名,例如 高浓铀(235 / 238U)。 该方法依赖于在诱导辐射脉冲之后的前1μs内的飞行时间测量,以及可以以比传统脉冲处理系统高得多的数据速率进行的中子和伽马射线的脉冲高度数据分析。 在100-500μs的时间范围内的热中子裂变提供了特殊核材料(如高浓缩铀)的独特签名。

    Method for producing actinium-225 and bismuth-213
    7.
    发明授权
    Method for producing actinium-225 and bismuth-213 失效
    锕-225和铋-213的制备方法

    公开(公告)号:US5355394A

    公开(公告)日:1994-10-11

    申请号:US916835

    申请日:1992-08-10

    CPC分类号: A61K51/1282 G21G1/06

    摘要: The invention relates to a method for producing actinium-225 and bismuth-213. According to the invention, radium-226 is irradiated in the thermal neutron flux of a nuclear reactor, the thorium fraction of the irradiation product is then chemically isolated and therefrom the actinium and radium mixture growing continuously by decay therein is chemically separated, this mixture serving as "cow" for the desired radionuclides which are growing continuously.

    摘要翻译: PCT No.PCT / EP91 / 00306 Sec。 371日期:1992年8月10日 102(e)日期1992年8月10日PCT 1991年2月18日提交PCT公布。 WO91 / 13443 PCT出版物 1991年9月5日,本发明涉及锕-225和铋-213的制造方法。 根据本发明,在核反应堆的热中子通量中照射镭-226,然后化学分离照射产物的钍馏分,由此通过其中的衰变连续生长的锕和镭混合物被化学分离,这种混合物 作为连续生长的所需放射性核素的“牛”。

    Segmented reaction chamber for radioisotope production

    公开(公告)号:US11862356B2

    公开(公告)日:2024-01-02

    申请号:US17228419

    申请日:2021-04-12

    IPC分类号: G21G1/08

    CPC分类号: G21G1/08

    摘要: A reactor that is operable to produce an isotope includes a region for containing a controlled nuclear fission reaction, the region segmented into a plurality of independent compartments, each of the compartments for containing a parent material in an aqueous solution that interacts with neutrons to produce the isotope via a fission reaction. Also provided are methods of producing an isotope using the same.

    DETECTORS, SYSTEMS, AND METHODS FOR CONTINUOUSLY MONITORING NEUTRONS WITH ENHANCED SENSITIVITY

    公开(公告)号:US20220285040A1

    公开(公告)日:2022-09-08

    申请号:US17191324

    申请日:2021-03-03

    发明人: Michael D. HEIBEL

    IPC分类号: G21G1/08 G01T3/00 G21C17/00

    摘要: A neutron detector is disclosed herein. The neutron detector can include a housing defining a cavity, wherein the housing is configured to permit an amount of neutrons emitted from a core of a nuclear reactor to enter the cavity. The neutron detector can also include an amount of a neutron sensitive material dispositioned within the cavity, wherein the neutron sensitive material is configured to generate and emit gamma rays upon interacting with the amount of neutrons. The neutron detector can further include an amount of electron emissive material configured to generate and emit a current of electrons upon interacting with the emitted gamma rays, wherein the current of electrons is indicative of the amount of neutrons emitted from the core of the nuclear reactor.