Method for Pre-separation of Nuclides in Spent Fuel

    公开(公告)号:US20240221966A1

    公开(公告)日:2024-07-04

    申请号:US18608909

    申请日:2024-03-18

    IPC分类号: G21F5/10 G21C17/06

    CPC分类号: G21F5/10 G21C17/06

    摘要: The present disclosure provides a method for pre-separating nuclides in spent fuel, comprising steps: S1. generating a temperature of 1200 to 1600° C. in a center of a fuel element, and at the same time introducing a cooling medium to an outer surface of the fuel element, to introduce a temperature difference to heat the fuel element; S2. soaking cooled spent fuel in an ionic liquid to selectively dissolve fission products and transuranic elements, so that the fission products and the transuranic elements are pre-separated from the spent fuel. The method achieves the effect of pre-separating part of the fission products and transuranic elements by physical methods, and solves the problem that homogenization in traditional post-processing technology causes obstacles to nuclide separation.

    METHOD AND SYSTEM FOR MEASURING MOISTURE CARRYOVER IN A NUCLEAR REACTOR

    公开(公告)号:US20230268090A1

    公开(公告)日:2023-08-24

    申请号:US17679784

    申请日:2022-02-24

    IPC分类号: G21C17/06 G01T1/16

    CPC分类号: G21C17/06 G01T1/16

    摘要: A method of measuring moisture carryover (MCO) in a nuclear reactor includes placing a first gamma detector adjacent to a steam conduit configured to transport steam generated by the core. The method additionally includes detecting a first amount of carryover gamma activity of a first quantity of sodium-24 in the steam within the steam conduit with the first gamma detector. The method also includes detecting a second amount of reference gamma activity of a second quantity of sodium-24 in a reference sample of reactor water from the core with a second gamma detector. The method further includes determining a flow rate of liquid water entrained in the steam based on the first amount of carryover gamma activity detected by the first gamma detector and the second amount of reference gamma activity detected by the second gamma detector.

    Insitu Process and System for the Dry Sampling & Characterization of Irradiated Zircaloy Pressure Tubes, Activated Alloy Metals and Graphite from Nuclear Reactor Components

    公开(公告)号:US20220148746A1

    公开(公告)日:2022-05-12

    申请号:US17094850

    申请日:2020-11-11

    IPC分类号: G21C17/06 G21C17/10 G21C19/02

    摘要: Disclosed is a process method and system for upfront sampling and characterization to selectively and representatively sample for activation levels of nuclear reactor core irradiated metal alloy internal components using a specialized robust hard metal reactor bit hollow tungsten carbide sampling head in conjunction with bespoke angled sampling gantry. The invention relates to the field of a nuclear reactor metal alloy vacuum hollow sampling head, sampling gantry, and retrieval system. The nuclear-activated metal alloys are drilled and sampled using a TruProBit® metal cutting drill bit. The long hollow drill bit with a hollow metal sampling head traverses the nuclear reactor metal layers and void spaces to cut and retrieve only metal alloy samples. The dry vacuumed airflow picks up the discrete incremental sample of metal filings, chips, and dust produced by the hollow metal cutting edges of the sampling head into a filter and then analyzed for radionuclides of concern.

    Standard for mobile equipment for measuring structural deformation of nuclear fuel assembly

    公开(公告)号:US11232876B2

    公开(公告)日:2022-01-25

    申请号:US16633487

    申请日:2017-09-29

    IPC分类号: G21C17/06 G01B11/16

    摘要: Provided is a standard for mobile equipment for measuring structural deformation of a nuclear fuel assembly, the standard including: a fixed frame fixed to one side of measuring equipment accommodated in a container; a standard member configured to be attached to and detached from the fixed frame, to rotate with one end portion of the fixed frame as a center, and to correspond to a nuclear fuel assembly standard specification, wherein an upper plate provided with a coupling means configured to be coupled with a transport device is coupled on one end portion of the standard member, a lower plate configured to be erected upright on and fixed to one side of the measuring equipment is coupled on an opposite end portion of the standard member.

    SYSTEM AND METHOD FOR PERFORMING ACTIVE SCANNING OF A NUCLEAR FUEL ROD

    公开(公告)号:US20210280329A1

    公开(公告)日:2021-09-09

    申请号:US17152008

    申请日:2021-01-19

    申请人: PHOENIX LLC

    IPC分类号: G21C17/06 G21G4/02 G21C3/326

    摘要: A system and method for performing active scanning on a nuclear fuel rod are provided. The system includes an electrically-driven neutron generator including an ion source, an accelerator, and a target; a moderator surrounding the neutron generator and configured to moderate neutrons generated by the neutron generator; a fuel rod channel disposed within the moderator, the fuel rod channel configured to receive a nuclear fuel rod and subject the nuclear fuel rod to a predetermined neutron flux; and a plurality of radiation detectors. When the nuclear fuel rod is subjected to the predetermined neutron flux, neutrons induce a secondary radiation of prompt and delayed gamma emissions, neutron emission, or a combination thereof that are detected by the plurality of radiation detectors to determine an amount of fissile material in the nuclear fuel rod and a spatial distribution of the fissile material along a length of the nuclear fuel rod.

    FUEL ROD SENSOR SYSTEM WITH INDUCTIVE COUPLING

    公开(公告)号:US20210074441A1

    公开(公告)日:2021-03-11

    申请号:US16564150

    申请日:2019-09-09

    IPC分类号: G21C17/10 G21C3/16 G21C17/06

    摘要: A sensor system for a fuel rod including a fuel pellet stack, the sensor system including a wireless interrogator disposed outside the fuel rod and a passive sensor component disposed within the fuel rod. The passive sensor component includes a receiver structured to receive an interrogation signal and output an excitation signal in response to receiving the interrogation signal, a reference transmitter structured to output a reference signal to the reference receiver in response to the excitation signal, a sensing transmitter structured to output a sensing signal to the sensing receiver in response to the excitation signal, and a core at least partially disposed within the sensing transmitter and coupled to move in conjunction with expansion or contraction of the fuel pellet stack, to move based on changes in pressure within the fuel rod, or to change temperature based on temperature changes within the fuel rod.