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.

    SYSTEMS AND METHODS FOR THE PRODUCTION OF ACID DEFICIENT URANYL NITRATE FROM A DILUTE URANYL NITRATE SOLUTION VIA DIFFUSION DIALYSIS AND VACUUM DISTILLATION

    公开(公告)号:US20240408548A1

    公开(公告)日:2024-12-12

    申请号:US18735908

    申请日:2024-06-06

    Applicant: X-energy, LLC

    Inventor: Alex TILTON

    Abstract: Systems and methods for producing acid deficient uranyl nitrate from a dilute uranyl nitrate solution are disclosed. In one form, the present disclosure provides a system comprising a feed evaporation system and a diffusion dialysis system. The feed evaporation system is configured to receive a feed stream and to boil off water, under vacuum, from the feed stream to produce a concentrated uranyl nitrate solution and a distilled water product. The diffusion dialysis system is configured to counter flow the concentrated uranyl nitrate solution and the distilled water product across a plurality of membrane vessels to promote nitrate migration from the concentrated uranyl nitrate solution to the distilled water, and to produce a dialysate stream and a recycle acid stream. The feed stream may include a product of a solvent extraction process used to recycle spent nuclear fuel and/or a recovery stream from other fuel fabrication activities.

    Method for decommissioning heavy water reactor facility

    公开(公告)号:US11984233B2

    公开(公告)日:2024-05-14

    申请号:US17259691

    申请日:2019-07-03

    CPC classification number: G21D1/003 G21F9/008

    Abstract: A method for decommissioning a heavy water reactor facility includes: removing the plurality of guide tubes from a plurality of through-holes; installing a plurality of shielding stoppers in the plurality of through-holes; removing the shielding stopper installed in one through-hole of the plurality of through-holes, and inserting a cutting device into a lower portion of the reactivity mechanism deck through the one through-hole to cut a connection portion between the reactivity mechanism deck and the calandria vault by using the cutting device; and separating the reactivity mechanism deck from the calandria vault.

    APPARATUS AND METHOD
    9.
    发明申请

    公开(公告)号:US20220181040A1

    公开(公告)日:2022-06-09

    申请号:US17440492

    申请日:2020-04-15

    Inventor: Ian Crabbe

    Abstract: An apparatus (10) is described for removing radioactive contamination, at least in part, from a first article (A1) comprising a metal, preferably wherein the metal comprises and/or is a low melting point metal for example lead and/or an alloy thereof. The apparatus (10) comprises a heated first vessel (100A) for melting the metal, at least in part, therein, thereby providing a melt (M) therefrom. The apparatus (10) comprises casting means (200) for forming a second article (A2), particularly a sheet, having a predetermined thickness (T), from the melt, preferably wherein the casting means (200) comprises and/or is a rotatable roller (210) arrangeable to contact the melt (M) to thereby form thereon the second article (A2) and a guide (220) arranged to remove the second article (A2) from the roller (210). The apparatus (10) comprises a set of radiation detectors (300), including a first radiation detector (300A), arranged to detect a first fraction of the radioactive contamination, if present, in a first part (P1) of a set of parts of the second article (A2), preferably wherein the set of radiation detectors (300) comprises opposed first and second radiation detectors (300A, 300B) arranged to receive the second article (A2) traversing therebetween. The apparatus (10) comprises a cutter (400) arrangeable to excise the first part (P1) of the second article (A2) therefrom.

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