THORIUM-BASED FUEL DESIGN FOR PRESSURIZED HEAVY WATER REACTORS

    公开(公告)号:US20240021328A1

    公开(公告)日:2024-01-18

    申请号:US18195112

    申请日:2023-05-09

    Abstract: Thorium-based fuel bundles are used in existing PHWR reactors (e.g., Indian 220 MWe PHWR, Indian 540 MWe PHWR, Indian 700 MWe PHWR, CANDU 300/600/900) in place of conventional uranium-based fuel bundles, with little or no modifications to the reactor. The fuel composition of such bundles is 60+ wt % thorium, with the balance of fuel provided by low-enriched uranium (LEU), which has been enriched to 13-19.95% 235U. According to various embodiments, the use of such thorium-based fuel bundles provides (1) 100% of the nominal power over the entire life cycle of the core, (2) high burnup, and (3) non-proliferative spent fuel bundles having a total isotopic uranium concentration of less than 12 wt %. Reprocessing of spent fuel bundles is also avoided.

    FUEL ELEMENT WITH MULTI-SMEAR DENSITY FUEL
    3.
    发明申请
    FUEL ELEMENT WITH MULTI-SMEAR DENSITY FUEL 审中-公开
    燃油元件与多中等密度燃油

    公开(公告)号:US20170062080A1

    公开(公告)日:2017-03-02

    申请号:US15245594

    申请日:2016-08-24

    Abstract: A fuel element has a ratio of area of fissionable nuclear fuel in a cross-section of the tubular fuel element perpendicular to the longitudinal axis to total area of the interior volume in the cross-section of the tubular fuel element that varies with position along the longitudinal axis. The ratio can vary with position along the longitudinal axis between a minimum of 0.30 and a maximum of 1.0. Increasing the ratio above and below the peak burn-up location associated with conventional systems reduces the peak burn-up and flattens and shifts the burn-up distribution, which is preferably Gaussian. The longitudinal variation can be implemented in fuel assemblies using fuel bodies, such as pellets, rods or annuli, or fuel in the form of metal sponge and meaningfully increases efficiency of fuel utilization.

    Abstract translation: 燃料元件具有在管状燃料元件的垂直于纵向轴线的横截面中的可裂变核燃料的面积与管状燃料元件的横截面中的内部容积的总面积的比率,其随着沿着 纵轴。 该比率可以随纵轴的位置而变化,最小值为0.30,最大值为1.0。 增加与常规系统相关的峰值燃耗位置之上和之下的比率减少了峰值燃尽和平坦化,并且使燃烧分布发生偏移,燃烧分布优选是高斯分布。 纵向变化可以在使用诸如颗粒,棒或环的燃料体的燃料组件或金属海绵形式的燃料中实现,并且有意义地提高燃料利用效率。

    SYSTEM AND METHOD FOR MAKING NUCLEAR FUEL ELEMENTS WITH A CONTROLLED NUMBER OF NUCLEAR PARTICLES

    公开(公告)号:US20230411024A1

    公开(公告)日:2023-12-21

    申请号:US17845385

    申请日:2022-06-21

    Applicant: X-Energy, LLC

    Inventor: Brandon Blamer

    CPC classification number: G21C3/045 G21C3/06 G01N15/14 G01N2015/1486

    Abstract: An optical counter is used in a method and system for producing a nuclear fuel element having a known volume of homogeneously distributed nuclear material. The method includes feeding nuclear fuel particles along a channel having a conveyer configured to transmit the nuclear fuel particles to an exit; driving the conveyer until a target number of nuclear fuel particles exits the channel through the exit; and counting a number of nuclear fuel particles which pass through the exit of the channel with an optical counter. The conveyer is stopped after the target number of nuclear fuel particles exits the channel. The target number of nuclear fuel particles are fed into a mold for shaping the nuclear fuel element, and void space remaining in the mold is filled with a particulate matrix material so as to homogeneously distribute the target number of nuclear fuel particles within the particulate matrix material. The particulate matrix material is then converted into a solid matrix material.

    Processing ultra high temperature zirconium carbide microencapsulated nuclear fuel

    公开(公告)号:US12068084B2

    公开(公告)日:2024-08-20

    申请号:US18140765

    申请日:2023-04-28

    CPC classification number: G21C3/623 G21C3/045 G21C3/07

    Abstract: The known fully ceramic microencapsulated fuel (FCM) entrains fission products within a primary encapsulation that is the consolidated within a secondary ultra-high-temperature-ceramic of Silicon Carbide (SiC). In this way the potential for fission product release to the environment is significantly limited. In order to extend the performance of this fuel to higher temperature and more aggressive coolant environments, such as the hot-hydrogen of proposed nuclear rockets, a zirconium carbide matrix version of the FCM fuel has been invented. In addition to the novel nature to this very high temperature fuel, the ability to form these fragile TRISO microencapsulations within fully dense ZrC represent a significant achievement.

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