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1. 发明申请

WO2013163475A1 NUCLEAR STEAM SUPPLY SYSTEM 审中-公开
标题翻译：核燃料供应系统
公开(公告)号：WO2013163475A1
公开(公告)日：2013-10-31
申请号：PCT/US2013/038289
申请日：2013-04-25
申请人： HOLTEC INTERNATIONAL, INC.
发明人： SINGH, Krishna, P. , RAJKUMAR, Joseph
IPC分类号： G21C15/24 , G21C15/02 , G21C5/22
CPC分类号： G21C15/24 , G21C15/26 , G21D1/006 , Y02E30/40
摘要： A nuclear steam supply system utilizing gravity-driven natural circulation for primary coolant flow through a fluidly interconnected reactor vessel and a steam generating vessel. In one embodiment, the steam generating vessel includes a plurality of vertically stacked heat exchangers operable to convert a secondary coolant from a saturated liquid to superheated steam by utilizing heat gained by the primary coolant from a nuclear fuel core in the reactor vessel. The secondary coolant may be working fluid associated with a Rankine power cycle turbine-generator set in some embodiments. The steam generating vessel and reactor vessel may each be comprised of vertically elongated shells, which in one embodiment are arranged in lateral adjacent relationship. In one embodiment, the reactor vessel and steam generating vessel are physically discrete self-supporting structures which may be physically located in the same containment vessel.
摘要翻译：一种使用重力驱动的自然循环的初级冷却剂流经流体互连的反应堆容器和蒸汽发生容器的核蒸汽供应系统。在一个实施例中，蒸汽发生容器包括多个垂直堆叠的热交换器，其可操作以通过利用来自反应堆容器中的核燃料芯的主要冷却剂所获得的热量将二次冷却剂从饱和液体转化为过热蒸汽。在一些实施例中，二次冷却剂可以是与兰金动力循环涡轮发电机组相关联的工作流体。蒸汽发生容器和反应堆容器可以各自包括垂直细长的外壳，在一个实施例中，它们以横向相邻的关系排列。在一个实施例中，反应堆容器和蒸汽发生容器是物理上离散的自支撑结构，其可以物理地位于相同的容纳容器中。

2. 发明申请

WO2019164617A3 COMPOSITE MODERATOR FOR NUCLEAR REACTOR SYSTEMS 审中-公开
公开(公告)号：WO2019164617A3
公开(公告)日：2019-08-29
申请号：PCT/US2019/014606
申请日：2019-01-22
申请人： ULTRA SAFE NUCLEAR CORPORATION
发明人： VENNERI, Francesco
IPC分类号： G21C1/14 , G21C1/16 , G21C1/20 , G21C1/24 , G21C1/26 , G21C1/28 , G21C5/20 , G21C5/22
摘要： A composite moderator medium for nuclear reactor systems and a method of fabricating a composite moderator block formed of the composite moderator medium The composite moderator medium includes two or more moderators, such as a low moderating material and a high moderating material. The high moderating material has a higher neutron slowing down power compared to the low moderating material. The low moderating material includes a moderating matrix of silicon carbide or magnesium oxide. The high moderating material is dispersed within the moderating matrix and includes beryllium, boron, or a compound thereof. The high moderating material is encapsulated within the low moderating material such that the high moderating material is not exposed outside of the low moderating material. The method can include selecting a sintering aid and a weight percent of the sintering aid in a composite moderator mixture based on the low moderating material and spark plasma sintering.

3. 发明申请

WO2021133797A1 MOLTEN FUEL REACTORS AND ORIFICE RING PLATES FOR MOLTEN FUEL REACTORS 审中-公开
公开(公告)号：WO2021133797A1
公开(公告)日：2021-07-01
申请号：PCT/US2020/066599
申请日：2020-12-22
申请人： TERRAPOWER, LLC
发明人： WARDLE, Kent E.
IPC分类号： G21C1/22 , G21C1/14 , G21C5/14 , G21C5/22 , G21C15/02 , G21C11/06
摘要： A molten fuel reactor includes a reactor core having substantially a right-circular cylinder shape with a longitudinal axis. At least one inlet is configured to channel fuel salt into the reactor core. At least one outlet is configured to channel fuel salt out of the reactor core, and the inlet and outlet at least partially define a flow loop of fuel salt with respect to the reactor core. An orifice ring plate is disposed within the reactor core and proximate the at least one inlet. The orifice ring plate is configured to condition a flow of fuel salt entering the reactor core from the at least one inlet. The orifice ring plate extends circumferentially about the longitudinal axis and has a height defined in a direction along the longitudinal axis. The orifice ring plate includes a plurality of apertures configured to allow the flow of fuel salt therethrough.

4. 发明申请

WO2021067903A1 NUCLEAR REACTOR CORE ARCHITECTURE WITH ENHANCED HEAT TRANSFER AND SAFETY 审中-公开
公开(公告)号：WO2021067903A1
公开(公告)日：2021-04-08
申请号：PCT/US2020/054190
申请日：2020-10-04
申请人： ULTRA SAFE NUCLEAR CORPORATION
发明人： VENNERI, Paolo, Francesco , EADES, Michael, John , SOUZA, Kelsey , DEASON, Wesley
IPC分类号： G21C1/06 , G21C1/12 , G21C3/58 , G21C5/22 , G21C3/60 , B64D27/22 , G21D5/06
摘要： An enhanced architecture for a nuclear reactor core includes several technologies: (1) nuclear fuel tiles (S-Block); and (2) a high-temperature thermal insulator and tube liners with a low-temperature solid-phase moderator (U-Mod) to improve safety, reliability, heat transfer, efficiency, and compactness. In S-Block, nuclear fuel tiles include a fuel shape designed with an interlocking geometry pattern to optimize heat transfer between nuclear fuel tiles and into a fuel coolant and bring the fuel coolant in direct contact with the nuclear fuel tiles. Nuclear fuel tiles can be shaped with discontinuous nuclear fuel lateral facets and have fuel coolant passages formed therein to provide direct contact between the fuel coolant and the nuclear fuel tiles. In U-Mod, tube liners with low hydrogen diffusivity retain hydrogen in the low-temperature solid- phase moderator even at elevated temperatures and the high-temperature thermal insulator insulates the solid-phase moderator from the nuclear fuel tiles.

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