REMOTE RESTART SYSTEM OF VITRIFICATION FACILITY AND METHOD FOR OPERATING SAME

    公开(公告)号:US20250069767A1

    公开(公告)日:2025-02-27

    申请号:US18721019

    申请日:2023-01-02

    Abstract: Provided are a remote restart system for vitrification equipment and a method of operating the same. The method of operating the remote restart system for the vitrification equipment includes: operating the vitrification equipment; and having power loss in the vitrification equipment, wherein the power loss occurs during or before operation of the vitrification equipment, the remote restart system assists in restarting the vitrification equipment when the power loss occurs in the vitrification equipment, and the remote restart system includes a low-temperature melting furnace, glass frit provided inside the low-temperature melting furnace, a titanium ring for heating the glass frit inside the low-temperature melting furnace, and a bar-shaped handling unit put into the low-temperature melting furnace to handle the glass frit to a state suitable for reignition of the glass frit.

    RADIATION SHIELD
    2.
    发明申请

    公开(公告)号:US20250064415A1

    公开(公告)日:2025-02-27

    申请号:US18818330

    申请日:2024-08-28

    Abstract: A radiation shield is adapted to be disposed transversely across a subject supported on the surface of a procedure table to protect medical professionals working in front of the radiation shield from radiation being applied to the subject behind the radiation shield. The radiation shield includes a movable barrier positional to extend transversely across a subject supported on the surface of a procedure table. The barrier has a generally vertically-oriented lower section; a generally forwardly sloping intermediate section; and a generally vertically-oriented upper section, forwardly offset from the plane of the lower section. A side section extends outwardly and rearwardly from one side of the lower, intermediate, and upper sections of the barrier. There is a recess in the lower edge of the lower section for accommodating a portion of the body of the subject on the surface of the procedure table, with portions of the lower section on each side of the recess projecting downwardly below the surface of the procedure table. A plurality of flexible radiopaque flaps depending from the perimeter of the recess block radiation from penetrating the gap between the subject and the perimeter of the recess.

    Continuous separation of radionuclides by shock electrodialysis

    公开(公告)号:US12237091B2

    公开(公告)日:2025-02-25

    申请号:US17105942

    申请日:2020-11-27

    Abstract: Radioactive nuclides (radionuclides) are separate from an aqueous radioactive liquid by feeding the liquid into a chamber between a porous anode and a porous cathode of a shock electrodialysis device. Meanwhile, an anolyte is fed through the porous anode, and a catholyte is fed through the porous cathode. A voltage is applied to the porous anode and to the porous cathode to create a voltage differential across the chamber. The liquid is passed through the chamber, and cations are selectively driven from the liquid into the cathode by the voltage differential. The voltage differential creates a desalination shock that produces an ion-enriched zone on one side of the desalination shock and a deionized zone on an opposite side. A brine including the radioactive cations is extracted from the ion-enriched zone through a brine outlet, and fresh water is extracted from the deionized zone through a fresh-water outlet.

    Method for pre-separation of nuclides in spent fuel

    公开(公告)号:US12230411B2

    公开(公告)日:2025-02-18

    申请号:US18608909

    申请日:2024-03-18

    Abstract: Nuclear reactors produce large amounts of spent fuel during operation. In addition to recyclable materials such as uranium and plutonium, spent fuel also contains significant amounts of fission products and highly radioactive transuranic (TRU) elements. Homogenization of nuclides in traditional post-processing technology hinders efficient fuel recycling. In order to improve the efficiency of spent fuel recycling, and to reduce the inevitable “highly radioactive waste” produced in existing spent fuel recycling processes, a novel method for pre-separating nuclides in spent fuel is disclosed. Specifically, we have developed a physical method, wherein an artificially created large temperature gradient drives the migration of fission gas bubbles in spent metallic nuclear reactor fuel. The fission gas bubbles preferentially carry fission products and transuranic elements to achieve effective pre-separation of these elements from spent fuel, lowering cost and improving efficiency of spent fuel recycling.

    Electromagnetic and radiation shielding using nanoforests

    公开(公告)号:US12225701B1

    公开(公告)日:2025-02-11

    申请号:US17696652

    申请日:2022-03-16

    Abstract: A lightweight radiation shielding material. A carbon nanotube forest is embedded in a matrix comprising nanoparticulates, such as nanoparticles, carbon nanotubes, or graphene nanosheets. The nanoparticulates can be low atomic number (low-Z) or high atomic number (high-Z). The matrix can be a solidified polymer, epoxy, resin, or ceramic precursor, for example silicon carbide. The radiation shield can shield an object from radio frequency interference (RFI), lightning, electromagnetic interference (EMI), an electromagnetic pulse (EMP), gamma rays, X-rays, neutrons, and/or protons. The nanoforest is disposed on a conductive base with sufficient in-plane electrical conductivity to provide an effective conductive path for currents induced by radiation absorption. The base can be a second nanoforest comprising horizontally-oriented carbon nanotubes, which makes the shield particularly lightweight, as low as 10% of the mass of aluminum that provides equivalent shielding. The base can be adhered to an object to be shielded.

    Storage and transport cask for nuclear waste

    公开(公告)号:US12217881B2

    公开(公告)日:2025-02-04

    申请号:US18451885

    申请日:2023-08-18

    Inventor: Krishna P. Singh

    Abstract: A nuclear waste cask in one embodiment includes an axially elongated cask body defining a longitudinally-extending opening forming an entrance to an internal storage cavity of the cask configured for holding radioactive nuclear waste materials. A closure lid detachably coupled to the cask body at the top opening seals the cavity. A cask locking mechanism includes a plurality of first locking protrusions spaced apart on the lid which are selectively interlockable with a plurality of second locking protrusions spaced apart on the cask body to lock the lid to the cask body. The first locking protrusions may be disposed on slideable locking bars moveable between locked and unlocked positions while the lid remains stationary on the cask body. Hydraulic or pneumatic actuators may be used to change position of the locking bars. The cask and lid may include other features such as impact absorbers and lifting elements.

    RADIOABSORBENT ASSEMBLIES
    10.
    发明申请

    公开(公告)号:US20250032070A1

    公开(公告)日:2025-01-30

    申请号:US18919281

    申请日:2024-10-17

    Abstract: A system of shields designed to provide substantially greater protection, head to toe, against radiation exposure to health care workers in a hospital room during procedures which require real-time imaging. The shields are placed around the patient and the x-ray table and provide protection even when the x-ray tube is moved to various angles around the patient.

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