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31. 发明申请

WO2021055806A1 NUCLEAR REACTOR PLENUM PLATE STANDOFF SPOOLS 审中-公开
公开(公告)号：WO2021055806A1
公开(公告)日：2021-03-25
申请号：PCT/US2020/051578
申请日：2020-09-18
申请人： BWXT NUCLEAR ENERGY, INC.
发明人： INMAN, James, Brian , DELESSIO, Steven, M. , WHITTEN, Andrew, C. , HAMILTON, Curtis, G.
IPC分类号： G21C3/33 , G21C1/08 , G21C3/32 , G21C3/322 , G21C3/334 , G21C5/00 , G21C5/10
摘要： A nuclear reactor having a pressure vessel, the reactor including a first plenum plate disposed within the pressure vessel, the first plenum plate defining a first plurality of apertures, a second plenum plate disposed within the pressure vessel, the second plenum plate being parallel to the first plenum plate and defining a first plurality of apertures, a fuel element including a fuel element flow tube extending through a first one of both the first pluralities of apertures of both the first and the second plenum plates, and a first fuel element standoff spool being disposed about a portion of the fuel element flow tube that is disposed between the first and the second plenum plates.

32. 发明申请

WO2020036361A1 REACTOR COOLANT SYSTEM AND NUCLEAR POWER PLANT HAVING THE SAME 审中-公开
公开(公告)号：WO2020036361A1
公开(公告)日：2020-02-20
申请号：PCT/KR2019/009854
申请日：2019-08-07
申请人： KOREA ATOMIC ENERGY RESEARCH INSTITUTE , KING ABDULLAH CITY FOR ATOMIC AND RENEWABLE ENERGY
发明人： KIM, Youngin , YOON, Hyungi , RYU, Seungyeob , BAE, Youngmin , MOON, Joohyung , HAN, Hunsik , SHIN, Soojai , CHANG, Cheongbong , KIM, Seok , KEE, Junewoo , CHO, Hyunjun , LEE, Minkyu , YOON, Juhyeon
IPC分类号： G21C15/243 , G21C1/08
摘要： The present discloser relates to a reactor coolant system. A reactor coolant system according to the present disclosure includes a reactor vessel configured to accommodate therein a core and a primary coolant carrying thermal energy generated from the core, a steam generator having a first flow path through which the primary coolant heated in the core flows, and a second flow path through which a secondary fluid changed from liquid to steam by exchanging heat with the primary coolant flows, a reactor coolant pump configured to circulate the primary coolant, and an inertia structure disposed on a flow path along which the primary coolant circulates, wherein the inertia structure is spaced apart from the reactor coolant pump.

33. 发明申请

WO2020009469A1 원자로 압력 용기의 폐기물 처리 장치 및 원자로 압력 용기의 폐기물 처리 방법 审中-公开
公开(公告)号：WO2020009469A1
公开(公告)日：2020-01-09
申请号：PCT/KR2019/008126
申请日：2019-07-03
申请人： 한국수력원자력 주식회사
发明人： 황영환 , 이미현 , 황석주 , 김천우
IPC分类号： G21D1/00 , G21C1/08
摘要： 원자로 압력 용기의 폐기물 처리 장치는 원자로 압력 용기의 하부를 관통하는 복수의 관통 배관들을 통해 상기 원자로 압력 용기 내부로 삽입되어 상기 원자로 압력 용기 내부의 폐기물을 흡입하는 흡입 유닛, 상기 흡입 유닛과 연결되어 상기 폐기물을 처리하는 폐기물 처리부, 및 상기 폐기물 처리부와 연결되어 상기 흡입 유닛을 사이에 두고 상기 원자로 압력 용기 하부에 위치하는 하부 수집부를 포함한다.

34. 发明申请

WO2019203576A1 가압 경수로형 원자력 발전소의 생체 보호 콘크리트의 해체 방법 审中-公开
公开(公告)号：WO2019203576A1
公开(公告)日：2019-10-24
申请号：PCT/KR2019/004659
申请日：2019-04-17
申请人： 한국수력원자력 주식회사
发明人： 황석주 , 홍성훈 , 이미현 , 김천우
IPC分类号： G21D1/00 , G21C1/08
摘要： 일 실시예에 따른 원자력 발전소의 생체 보호 콘크리트의 해체 방법은 원자로를 둘러싸는 생체 보호 콘크리트에 설치된 중성자 감지 위치 조절기를 해체하여 상기 생체 보호 콘크리트에 복수개의 관통부를 형성하는 단계, 상기 복수개의 관통부로 절단 장치의 일부를 투입하는 단계, 그리고 상기 절단 장치를 이용하여 상기 생체 보호 콘크리트를 복수개의 서브 콘크리트로 분해하는 단계를 포함한다.

35. 发明申请

WO2017155643A1 REACTOR COOLANT SYSTEM PIPING TEMPERATURE DISTRIBUTION MEASUREMENT SYSTEM 审中-公开
标题翻译：反应堆冷却剂系统管道温度分布测量系统
公开(公告)号：WO2017155643A1
公开(公告)日：2017-09-14
申请号：PCT/US2017/016329
申请日：2017-02-03
申请人： WESTINGHOUSE ELECTRIC COMPANY LLC
发明人： CARVAJAL, Jorge V. , HEIBEL, Michael D. , ARLIA, Nicola G. , WALTER, Melissa M. , FLAMMANG, Robert W. , JAMES, Michael A. , SUMEGO, David M.
IPC分类号： G21C17/022 , G21C15/18 , G21C1/08
摘要： A system that measures the temperature distribution of the reactor coolant flowing through the hot leg or cold leg pipes by measuring the speed of sound time delay. This concept uses radiation hardened and temperature tolerant ultrasonic signal drivers based on vacuum micro-electronic technology. The system employs ultrasonic signals propagated through water, and relies on the characteristic that the speed of sound changes as the density and temperature of the water changes. Thus, a measured difference in the speed of sound in water may be directly correlated to a temperature change of the water.
摘要翻译：通过测量声音时间延迟的速度来测量流经热支管或冷支管的反应堆冷却剂的温度分布的系统。该概念使用基于真空微电子技术的抗辐射和耐高温的超声波信号驱动器。该系统采用通过水传播的超声信号，并且依赖于声速随着水的密度和温度变化而变化的特性。因此，测量到的水中声速的差异可能与水的温度变化直接相关。

36. 发明申请

WO2013162894A1 INSTRUMENTATION AND CONTROL PENETRATION FLANGE FOR PRESSURIZED WATER REACTOR 审中-公开
标题翻译：用于加压水反应器的仪器和控制渗透法兰
公开(公告)号：WO2013162894A1
公开(公告)日：2013-10-31
申请号：PCT/US2013/036062
申请日：2013-04-11
申请人： WESTINGHOUSE ELECTRIC COMPANY LLC
发明人： CONWAY, Lawrence, E. , HARKNESS, Alexander, W.
IPC分类号： G21C1/08
CPC分类号： G21C13/028 , G21C1/322 , G21C7/12 , G21C13/036 , G21C17/116 , Y02E30/40
摘要： A nuclear reactor having a penetration seal ring interposed between the reactor vessel flange and a mating flange on the reactor vessel head. Radial ports through the flange provide passage into the interior of the reactor vessel for utility conduits that can be used to convey signal cables, power cables or hydraulic lines to the components within the interior of the pressure vessel. A double o-ring seal is provided on both sides of the penetration flange and partial J-welds on the inside diameter of the flange between the flange and the utility conduits secure the pressure boundary.
摘要翻译：一种核反应堆，其具有插入在反应堆容器凸缘和反应堆容器头部的配合凸缘之间的穿透密封环。通过凸缘的径向通道提供通向反应堆容器的内部，用于可用于将信号电缆，电力电缆或液压管线传送到压力容器内部的部件的公用管道。在穿透法兰的两侧设有双O型圈密封件，法兰和公用管道之间法兰内径上的部分J型焊缝固定压力边界。

37. 发明申请

WO2005050667A3 SYSTEM AND METHOD FOR ESTIMATING HELIUM PRODUCTION IN STAINLESS STEEL CORE SHROUDS OF NUCLEAR REACTORS 审中-公开
标题翻译：不锈钢核心核反应堆生产氦生产系统及方法
公开(公告)号：WO2005050667A3
公开(公告)日：2005-09-29
申请号：PCT/US2004037879
申请日：2004-11-12
申请人： GEN ELECTRIC , SITARAMAN SHIVAKUMAR , CHIANG REN-TAI , JENKINS ALTON LEWIS
发明人： SITARAMAN SHIVAKUMAR , CHIANG REN-TAI , JENKINS ALTON LEWIS
IPC分类号： G21C17/003 , G01N33/20 , G21C20060101 , G21C1/08 , G21C17/00 , G21C17/01 , G21C19/00 , G21D1/00
CPC分类号： G21C17/00 , G21C17/003 , G21C17/01 , G21D3/001 , G21Y2002/104 , G21Y2002/303 , G21Y2004/40 , Y02E30/40
摘要： A method (70) for estimating a helium content of the stainless steel core shroud (20) in a boiling water nuclear reactor includes, in an exemplary embodiment, determining (72) a neutron fluence for predetermined areas of the reactor, and estimating (74) a helium content of the stainless steel shroud at predetermined areas of the reactor using the following equation: CHe =1031 * (1- e J* J), where CHe is the helium concentration as atomic parts per billion of helium in the stainless steel shroud per weight parts per million of boron in the stainless steel shroud, bj is a value between about 2.50e and about 5.00e , phij is fluence expressed as neutrons per square centimeter, and subscript j denotes thermal fluence or fast fluence.
摘要翻译：在示例性实施例中，用于估计沸水核反应堆中的不锈钢芯护罩（20）的氦含量的方法（70）包括确定（72）反应堆的预定区域的中子注量，并估计（74 ）使用以下等式，在反应器的预定区域处的不锈钢护罩的氦含量：CHe = 1031 *（1-e-> J *øJ），其中CHe是氦浓度为原子不锈钢护罩中每盎司百万分之一硼的不锈钢护罩中的十亿分之几氦，bj为约2.50e〜约5.00e <-21之间的值，phij为中子表示的能量密度每平方厘米，下标j表示热能通量或快速注量。

38. 发明申请

WO0118820A3 UNITARY, TRANSPORTABLE, ASSEMBLED NUCLEAR STEAM SUPPLY SYSTEM WITH LIFE TIME FUEL SUPPLY AND METHOD OF OPERATING SAME 审中-公开
标题翻译：一次性，可运输，组装寿命为一年的燃料供应系统和操作方法相同的核蒸汽供应系统
公开(公告)号：WO0118820A3
公开(公告)日：2001-10-04
申请号：PCT/US0019798
申请日：2000-07-20
申请人： WESTINGHOUSE ELECTRIC CORP
发明人： CARELLI MARIO D , GREEN LAWRENCE , PARAMONOV DMITRY V , ZHAN NELSON J
IPC分类号： G21C1/00 , G21C1/08 , G21C1/32 , G21C15/18
CPC分类号： G21C1/322 , G21C1/086 , G21C15/18 , Y02E30/32
摘要： A unitary, transportable, assembled nuclear steam supply system (NSSS) with a lifetime fuel supply utilizes a fast or epithermal spectrum reactor core immersed in a pool of light water together with a plurality of steam generators through which the coolant is circulated by up to 100 % natural circulation at full power, augmented by reactor coolant pumps also immersed in the pool. Redundant steam generators and reactor coolant pumps, together with the fast or epithermal spectrum reactor core and pool configuration, make it possible to operate the NSSS for 10 to 15 or more years without maintenance on the internals or refueling, thereby rendering the system proliferation resistant.
摘要翻译：具有终身燃料供应的整体的，可运输的，组装的核蒸汽供应系统（NSSS）利用浸入轻水池中的快速或超热光谱反应堆芯与多个蒸汽发生器一起使冷却剂循环达到100 全功率自然循环％，反应堆冷却剂泵也浸入池中。冗余蒸汽发生器和反应堆冷却剂泵，以及快速反应堆或超热反应堆堆芯和水池配置，使NSSS运行10-15年或更长时间，而无需维护内部部件或加油，从而使系统能够抗扩散。

39. 发明申请

WO01018820A2 UNITARY, TRANSPORTABLE, ASSEMBLED NUCLEAR STEAM SUPPLY SYSTEM WITH LIFE TIME FUEL SUPPLY AND METHOD OF OPERATING SAME 审中-公开
标题翻译：单位，运输，装配时间燃料供应的核燃料供应系统及其操作方法
公开(公告)号：WO01018820A2
公开(公告)日：2001-03-15
申请号：PCT/US2000/019798
申请日：2000-07-20
IPC分类号： G21C1/00 , G21C1/08 , G21C1/32 , G21C15/18 , G21C
CPC分类号： G21C1/322 , G21C1/086 , G21C15/18 , Y02E30/32
摘要： A unitary, transportable, assembled nuclear steam supply system (NSSS) with a lifetime fuel supply utilizes a fast or epithermal spectrum reactor core immersed in a pool of light water together with a plurality of steam generators through which the coolant is circulated by up to 100 % natural circulation at full power, augmented by reactor coolant pumps also immersed in the pool. Redundant steam generators and reactor coolant pumps, together with the fast or epithermal spectrum reactor core and pool configuration, make it possible to operate the NSSS for 10 to 15 or more years without maintenance on the internals or refueling, thereby rendering the system proliferation resistant.
摘要翻译：具有终身燃料供应的单一，可运输，组装的核蒸汽供应系统（NSSS）利用浸入淡水池中的快速或超热频谱反应堆核心，以及多个蒸汽发生器，冷却剂通过该蒸汽发生器循环达100 全功率的自然循环％，也被沉浸在池中的反应堆冷却剂泵增加。冗余蒸汽发生器和反应堆冷却剂泵以及快速或超热谱反应堆核心和池配置可以使NSSS运行10到15年或更长时间，而不需要对内部维护或加油进行维护，从而使系统具有增殖能力。

40. 发明申请

WO99053502A3 HEAD ASSEMBLY FOR A NUCLEAR REACTOR PRESSURE VESSEL 审中-公开
标题翻译：用于核反应堆压力容器的头部组件
公开(公告)号：WO99053502A3
公开(公告)日：1999-12-16
申请号：PCT/US1999/007119
申请日：1999-03-31
IPC分类号： G21C1/00 , G21C1/08 , G21C7/12 , G21C13/00 , G21C13/073
CPC分类号： G21C7/12 , G21C13/073 , G21Y2002/201 , G21Y2002/202 , G21Y2002/304 , G21Y2002/402 , G21Y2002/501 , G21Y2004/30 , Y02E30/39
摘要： An integrated head assembly (14) for a nuclear reactor pressure vessel (10) includes a closure head (20) with CRDM assemblies (22) extending upwardly from the head. A CRDM seismic support (24) disposed above the closure head provides lateral support for the CRDM assemblies. The seismic support also has air flow holes which communicate with the interior of a shroud (32) enclosing the CRDMs and extending upwardly from the closure head to the seismic. The shroud has an air port (96) in direct air flow communication with the surrounding atmosphere so that the closure head, shroud and seismic support define an air flow passageway directly communicating with the surrounding atmosphere via the air port and without the extensive ductwork and, therefore, with substantially less power. A missile shield (26) disposed above and in air flow communication with the seismic support provides a lightweight, compact physical barrier for removing energy from dislocated objects such as CRDM drive rods.
摘要翻译：用于核反应堆压力容器（10）的集成头组件（14）包括具有从头部向上延伸的CRDM组件（22）的封闭头（20）。设置在封闭头上方的CRDM地震支架（24）为CRDM组件提供横向支撑。地震支架还具有气流孔，其与包围CRDM的护罩（32）的内部连通，并从闭合头向上延伸到地震。护罩具有与周围空气直接气流连通的空气口（96），使得封闭头，护罩和地震支架限定通过空气口直接与周围大气连通并且没有广泛的管道系统的空气流通道，因此，功率大大降低。设置在地震支架上方并与空气流连通的导弹屏蔽件（26）提供了轻量级的紧凑的物理屏障，用于从诸如CRDM驱动杆的位错物体移除能量。

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