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1. 发明申请

WO2018071081A2 FUEL-COOLED NEUTRON REFLECTOR 审中-公开
标题翻译：燃料冷却的中子反射镜
公开(公告)号：WO2018071081A2
公开(公告)日：2018-04-19
申请号：PCT/US2017/042097
申请日：2017-07-14
申请人： ELYSIUM INDUSTRIES LTD.
发明人： DODSON, Andrew, McCall , LOWREY, Justin , WANGARD, William , LEVESQUE, Mark
IPC分类号： G21C7/06
CPC分类号： G21C11/06 , G21C1/02 , G21C3/24 , G21C15/10 , Y02E30/40
摘要： A nuclear reactor is provided that uses a liquid fuel and includes a neutron reflector that reflects neutrons in towards a core of the reactor. The neutron reflector can include louvers that create channels or passages through the neutron reflector such that the liquid fuel tends to flow through neutron reflector and remove heat from the neutron reflector. The liquid fuel can carry heat away from the neutron reflector, through the core of the reactor, and onwards to an intended heat exchange mechanism of the reactor. The louvers and passages can help to channel the moving fluid throughout the volume of the reactor and to prevent stagnant eddies in which undisturbed pockets of fuel can otherwise turn into unwanted hot spots.
摘要翻译：提供了一种使用液体燃料并包括中子反射器的核反应堆，该中子反射器将中子反射向反应堆的核心。中子反射器可以包括百叶窗，该百叶窗形成通过中子反射器的通道或通道，使得液体燃料倾向于流过中子反射器并且从中子反射器移除热量。液体燃料可以将热量从中子反射器传送出去，通过反应器的核心并且向前传送到反应器的预期热交换机构。百叶窗和通道可以帮助引导流动的流体遍及反应器的体积并且防止停滞的涡流，其中未扰动的燃料袋可能会变成不需要的热点。

2. 发明申请

WO2018071081A3 FUEL-COOLED NEUTRON REFLECTOR 审中-公开
公开(公告)号：WO2018071081A3
公开(公告)日：2018-04-19
申请号：PCT/US2017/042097
申请日：2017-07-14
申请人： ELYSIUM INDUSTRIES LTD.
发明人： DODSON, Andrew, McCall , LOWREY, Justin , WANGARD, William , LEVESQUE, Mark
IPC分类号： G21C11/06 , G21C15/02 , G21C15/10
摘要： A nuclear reactor is provided that uses a liquid fuel and includes a neutron reflector that reflects neutrons in towards a core of the reactor. The neutron reflector can include louvers that create channels or passages through the neutron reflector such that the liquid fuel tends to flow through neutron reflector and remove heat from the neutron reflector. The liquid fuel can carry heat away from the neutron reflector, through the core of the reactor, and onwards to an intended heat exchange mechanism of the reactor. The louvers and passages can help to channel the moving fluid throughout the volume of the reactor and to prevent stagnant eddies in which undisturbed pockets of fuel can otherwise turn into unwanted hot spots.

3. 发明申请

WO2018026536A1 ACTINIDE RECYCLING SYSTEM 审中-公开
标题翻译： ACTINIDE回收系统
公开(公告)号：WO2018026536A1
公开(公告)日：2018-02-08
申请号：PCT/US2017/043121
申请日：2017-07-20
申请人： ELYSIUM INDUSTRIES LTD.
发明人： SIMPSON, Michael, F. , DODSON, Andrew , WANGARD, William , PHEIL, Ed , HANSON, Michael
IPC分类号： C22B26/20 , C22B26/10 , G21F9/12 , C22B15/00
CPC分类号： C22B60/02 , C22B7/00 , C25B1/26 , C25C3/34 , C25C7/025 , G21F9/12 , G21F9/308 , Y02P10/212
摘要： Systems and methods are provided for recycling actinides from molten chloride fuel salts that have been employed as fuel within a molten salt nuclear reactor. The used molten chloride fuel salts can contain soluble fission products (e.g., non-actinide fission products) that contaminate the molten chloride fuel salt mixture, as well as recoverable actinide chlorides. In one aspect, the contaminating non-actinide fission products can be separated from the molten chloride fuel salt mixture. Subsequently, actinide chlorides remaining within the molten fuel salts can be partitioned into a liquid bismuth phase. These actinides can then be re-chlorinated (e.g., oxidized) to strip them out of the liquid bismuth phase and into a clean molten chloride salt mixture that does not contain contaminating non-actinide fission products and that can be pumped back to the nuclear reactor core as fuel.
摘要翻译：提供了系统和方法，用于从在熔盐核反应堆内用作燃料的熔融氯化物燃料盐回收act系元素。所使用的熔融氯化物燃料盐可含有污染熔融氯化物燃料盐混合物的可溶裂变产物（例如非act系元素裂变产物）以及可回收的act系元素氯化物。在一个方面，污染的非act系元素裂变产物可以从熔融氯化物燃料盐混合物中分离出来。随后，保留在熔融燃料盐内的act系元素氯化物可以分配成液态铋相。然后可以将这些act系元素重新氯化（例如氧化）以将它们从液态铋相中除去并且进入不含有污染的非act系元素裂变产物并且可以被泵回到核反应堆的清洁的熔融氯化物盐混合物中核心作为燃料。

4. 发明申请

WO2017205706A1 HEAT REMOVAL SYSTEM FOR A MOLTEN SALT REACTOR SYSTEM 审中-公开
标题翻译：一种熔盐反应堆系统的除热系统
公开(公告)号：WO2017205706A1
公开(公告)日：2017-11-30
申请号：PCT/US2017/034606
申请日：2017-05-26
申请人： ELYSIUM INDUSTRIES LTD.
发明人： WANGARD, William , DODSON, Andrew, McCall
IPC分类号： G21C15/18 , F28D9/00 , F28D21/00 , G21C3/54 , G21C15/00
CPC分类号： G21C15/18 , F28D2021/0054 , G21C3/54 , Y02E30/40
摘要： A heat removal system for use in molten salt reactor (MSR) system and configured to passively transfer of heat away from a reactor core to prevent elevated temperatures within the reactor core, thereby reducing the risk of catastrophic failure of the reactor.
摘要翻译：用于熔盐反应堆（MSR）系统并被配置成被动地将热量从反应堆堆芯转移出去以防止反应堆堆芯内升高的温度，从而降低灾难性故障风险的排热系统的反应堆。

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