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1. 发明公开

EP0232970A3 Compact small pressurized water nuclear power plant 有权
标题翻译：紧凑型小型水力发电厂
公开(公告)号：EP0232970A3
公开(公告)日：1987-11-25
申请号：EP87300211
申请日：1987-01-09
申请人： WESTINGHOUSE ELECTRIC CORPORATION
发明人： Tower, Stephen Nelson , Veronesi, Luviano
IPC分类号： G21C01/08 , F22B01/02
CPC分类号： F22B1/025 , G21C1/08 , G21D5/08 , Y02E30/32
摘要： A nuclear rector steam generating plant including a pressurized water reactor (3) with a single discharge line (5) to a steam generator (7), with the primary coolant passing through the steam generator being divided into two streams in the channel head outlet section that is divided into two subsections. Discharge nozzles on the outlet subsections direct the streams of coolant to two separate pumps (29, 31) which pump the primary coolant back to the reactor (3). Operational safety is greatly improved with this arrangement, especially for smaller one- or two-loop plants.

2. 发明公开

EP0057369A3 Improved valve support arrangement for pressurizer in a nuclear power plant 有权
标题翻译：改进的核电厂压力机的阀支撑装置
公开(公告)号：EP0057369A3
公开(公告)日：1982-10-27
申请号：EP82100338
申请日：1982-01-19
申请人： WESTINGHOUSE ELECTRIC CORPORATION
发明人： Zegar, Martin Joseph , Kish, Nicholas William , Rusnica, Edward Joseph , Sarver, Stephen Jack , Jenkins, Howard Stanley
IPC分类号： G21C01/08 , G21C13/02
CPC分类号： G21C13/024 , G21C1/09 , Y02E30/40
摘要： A modularly constructable support arrangement is provided for pressurizer safety and relief valves in a nuclear power plant. A common header is supported by four sets of columnar legs which are secured to pressurizer vessel side wall lugs. The safety and relief valves are securely disposed and connected through short pipe runs to discharge steam into the header.

3. 发明公开

EP0240335A3 Pressurized water reactor having improved calandria assembly 失效
标题翻译：具有改进的卡车装配的加压水反应器
公开(公告)号：EP0240335A3
公开(公告)日：1988-09-28
申请号：EP87302834
申请日：1987-04-01
申请人： WESTINGHOUSE ELECTRIC CORPORATION
发明人： Gillett, James Edwin , Goossen, John E.
IPC分类号： G21C05/10 , G21C01/08 , G21C15/18
CPC分类号： G21C1/086 , G21C5/10 , G21C15/18 , Y02E30/32
摘要： A nuclear reactor with control-rods movable into and out of its core has a calandria structure (50) above the area of movement of the control-rods. The coolant flow from the core remains axially upward in the area of movement of the control-rods. Radial coolant flow occurs through the calandria (50) past the tubes (56) between upper and lower calandria plates (54, 52) which receive the drive shafts (200, 201) for the control-rods so as to protect the drive shafts (200, 201) from the transverse flow of coolant within the calandria (39). Connecting tubes (60, 61) surround the drive shafts (200, 201) above the calandria (50) and at least some of the connecting tubes (66, 61) have flow holes (221) just above the calandria and diverter means (222) disposed within so as to prevent water from jetting directly onto the drive shafts (200,201).

4. 发明公开

EP0212949A3 Pressurized water nuclear reactor pressure control system and method of operating same 失效
标题翻译：加压水核反应堆压力控制系统及其运行方法
公开(公告)号：EP0212949A3
公开(公告)日：1988-02-24
申请号：EP86306283
申请日：1986-08-14
申请人： WESTINGHOUSE ELECTRIC CORPORATION
发明人： Kish, Nicholas William
IPC分类号： G21C01/08
CPC分类号： G21C1/09 , Y02E30/40 , Y10T137/4516 , Y10T137/4576
摘要： A pressure control system for a pressurized water nuclear reactor for quickly closing the valves (33) associated with the pressurizer (3) thereof has a temperature detection device (45) on the loop seal (23) of each valve (33) and water supply piping (35) including a valve (43) responsive thereto to charge water to the loop seal (23) upon a temperature rise therein and to stop the flow of water in the loop seal (23) upon a temperature drop therein. The rapid supply of water to the loop seals for the valves protects the valve seats from wear and degradation and prolongs the life thereof.

5. 发明公开

EP0205900A3 Pressure control system for a pressurized water nuclear reactor plant 失效
标题翻译：一种加压水核反应堆的压力控制系统
公开(公告)号：EP0205900A3
公开(公告)日：1987-12-09
申请号：EP86106637
申请日：1986-05-15
申请人： WESTINGHOUSE ELECTRIC CORPORATION
发明人： Schwab, John Allen
IPC分类号： G21C01/08
CPC分类号： G21C1/09 , Y02E30/40 , Y10S261/76
摘要： An improved pressure control system (1) for a pressurized water nuclear reactor plant contains a two stage sparger in a pressurizer relief tank. The two stage sparger has a primary conduit (31) and secondary conduit (37), both of which have orifices (33,44) and an intermediate valve (49) that is responsive to a pressure differential between the two conduits (31, 37), the secondary conduit being preferably of a diameter less, but having a larger area of orifices.

6. 发明申请

WO1997002575A1 A METHOD FOR THE DESTRUCTION OF PLUTONIUM BY IRRADIATION IN A LIGHT WATER REACTOR 审中-公开
标题翻译：一种在轻水反应器中通过辐射破坏钚的方法
公开(公告)号：WO1997002575A1
公开(公告)日：1997-01-23
申请号：PCT/EP1996002915
申请日：1996-07-03
申请人： EUROPEAN ATOMIC ENERGY COMMUNITY (EURATOM) , MAGILL, Joseph , MATZKE, Hansjoachim , NICOLAOU, George , PEERANI, Paolo , VAN GEEL, Jacques
发明人： EUROPEAN ATOMIC ENERGY COMMUNITY (EURATOM)
IPC分类号： G21C01/08
CPC分类号： G21C1/08 , G21C3/326 , G21Y2002/60 , G21Y2004/60 , Y02E30/38
摘要： This invention relates to a method for the destruction of plutonium (Pu) by irradiation in a light water reactor (LWR). According to the invention Pu is mixed with highly enriched uranium (U) in roughly equal weight proportion rates. This mixture is embedded in an inert matrix of a material whose components have an atomic number significantly lower than 92. LWR fuel pins are then produced therefrom and these pins are inserted in a LWR in place of certain normal LWR fuel pins. The irradiation time of the fuel pins containing Pu is significantly longer than that of said normal pins. The irradiation is preferably repeated after about 200 years without any reprocessing of the spent fuel.
摘要翻译：本发明涉及通过在轻水反应堆（LWR）中照射来破坏钚（Pu）的方法。根据本发明，Pu与高浓缩铀（U）以大致相等的重量比混合。将该混合物嵌入材料的惰性基质中，其组分的原子数显着低于92.然后由其产生LWR燃料销，并将这些销插入LWR中代替某些正常的LWR燃料销。包含Pu的燃料销的照射时间明显长于所述普通销的照射时间。大约200年之后，优选重复照射，而没有对废燃料进行任何后处理。

7. 发明申请

WO1979000742A1 FUEL ASSEMBLY 审中-公开
标题翻译：燃油总成
公开(公告)号：WO1979000742A1
公开(公告)日：1979-10-04
申请号：PCT/JP1979000038
申请日：1979-02-19
申请人： HITACHI LTD , YAMASHITA J , YOKOMI M , KAWAI T
发明人： HITACHI LTD
IPC分类号： G21C01/08
CPC分类号： G21C7/005 , G21C3/32 , G21C3/328 , G21Y2002/201 , G21Y2002/50 , G21Y2004/10 , Y02E30/38 , Y02E30/39 , Y10S376/917
摘要： It is preferable, in a high burn-up degree range, that the output distribution curve in the axial direction of a reactor be flat. To this end, a mean infinite multiplication factor in an upper area in the axial direction of a core should be made lower than a mean infinite multiplication factor in a lower area, in view of the fact that volume coefficient has a distribution along the axial direction. It particularly becomes possible by lowering a mean enrichment of fuel located at the upper area with respect to a mean enrichment of fuel located at the lower area.
摘要翻译：在高燃耗程度范围内，反应器轴向的输出分布曲线优选平坦。为此，考虑到体积系数具有沿着轴向的分布的事实，在芯部的轴向方向上的上部区域中的平均无限倍增系数应该低于下部区域中的平均无限倍增因子。相对于位于下部区域的燃料的平均富集，可以降低位于上部区域的燃料的平均富集特别成为可能。

8. 发明申请

WO1998001863A1 METHOD FOR GENERATING STEAM FROM THE HEAT RELEASED BY A NUCLEAR REACTOR CORE AND NUCLEAR REACTOR FOR IMPLEMENTING THE METHOD 审中-公开
标题翻译：用于由核反应堆芯和核反应堆释放的热量产生蒸汽的方法，用于实施方法
公开(公告)号：WO1998001863A1
公开(公告)日：1998-01-15
申请号：PCT/FR1997001212
申请日：1997-07-04
申请人： FRAMATOME , BONHOMME, Nicolaas
发明人： FRAMATOME
IPC分类号： G21C01/08
CPC分类号： G21C1/08 , G21D5/08 , G21Y2002/301 , G21Y2002/50 , G21Y2004/305 , G21Y2004/40 , Y02E30/40
摘要： The invention discloses a method for generating steam from the heat released by a nuclear reactor core and a nuclear reactor for implementing the method. The cooling water is circulated in a primary circuit, in contact with the reactor core and with a heat exchanging surface between the reactor cooling water and the supply water that is heated and evaporated by being in contact with the heat exchanging surface. The cooling water circulating in the primary circuit is at a temperature and a pressure close to the temperature and the pressure of the water ebullition curve. The compactly built nuclear reactor comprises steam generators (26) but has no pressure maintaining device. Preferably, the hot (29) and cool (31) branches are rectilinear and concentric, The compactly built nuclear reactor is located in a metal containment shell.(40).
摘要翻译：本发明公开了一种由核反应堆核心和核反应堆释放的热量产生蒸汽的方法，用于实施该方法。冷却水在初级回路中循环，与反应堆芯接触，并且通过与热交换表面接触而被加热和蒸发的反应器冷却水和供水之间的热交换表面循环。在一次循环中循环的冷却水处于接近于水沸腾曲线的温度和压力的温度和压力。紧凑的核反应堆包括蒸汽发生器（26），但没有压力维持装置。优选地，热（29）和冷（31）分支是直线的和同心的。紧凑的核反应堆位于金属容纳壳中（40）。

9. 发明申请

WO1996009628A1 NATURAL CIRCULATION REACTOR, ESPECIALLY BOILING WATER REACTOR, AND PROCESS FOR REGULATING THE CORE COOLANT FLOW RATE OF A NATURAL CIRCULATION REACTOR 审中-公开
标题翻译：自然循环反应器中，特别是沸水反应器，和方法用于调节自然循环反应堆的堆芯的冷却剂流
公开(公告)号：WO1996009628A1
公开(公告)日：1996-03-28
申请号：PCT/DE1995001298
申请日：1995-09-21
申请人： SIEMENS AKTIENGESELLSCHAFT , PALAVECINO, Carlos , SCHMIDT, Herbert
发明人： SIEMENS AKTIENGESELLSCHAFT
IPC分类号： G21C01/08
CPC分类号： G21C1/084 , G21C15/02 , G21Y2002/203 , G21Y2002/304 , G21Y2004/30 , G21Y2004/402 , Y02E30/31
摘要： The invention relates to a natural circulation reactor (1), especially a boiling water reactor, with a reactor pressure vessel (2), a reactor core (3) and a core jacket (4) surrounding said reactor core (3), which is arranged inside the reactor pressure vessel (2) and has at least one inlet (5) and one outlet (6) for core coolant. A flow path (8) for core coolant (7) formed between the core jacket (4) and the reactor pressure vessel (3) leading further through the inlet (5) has a flow cross section (9) with at least one throttle element (10) fitted in the flow path (8) by means of which the flow cross section (9) can be altered to regulate the flow rate of the core coolant. By altering the cross-sectional area of the throttle element (10) it is possible to reduce and increase the flow cross section (9) so that the power of the natural circulation reactor can easily be regulated and a power reduction to about 40 % of the momentary reactor power is ensured in the event of an incident. The invention also relates to a process for regulating the core coolant flow through a reactor core (3) of a natural circulation reactor.
摘要翻译：本发明涉及一种自然循环反应器（1），特别是沸水反应器中，（2），反应器核心（3）和（3）包围所述芯套的反应堆堆芯（4）设置在反应器压力容器（2）内的反应器压力容器被布置和至少一个为芯冷却剂入口开口（5）和出口开口（6）具有。 A中的芯套（4）和（3）所形成的反应器压力容器中，并进入芯套（4）通过所述进入口（5）进一步导致对于堆芯冷却剂的流路（8）（7）之间有一个流动横截面（9），（在流路8 ）至少一个节流元件（10）被布置成，通过所述用于调节所述芯的冷却剂流量的流横截面（9）是可变的。是通过改变节流元件（10），所述流动横截面均为减小和增大，因此，自然循环反应器的功率调节以简单的方式实现，并保证在Störfalll功率减小瞬时反应堆功率的大约40％的横截面面积。本发明还涉及一种用于通过自然循环反应堆的反应堆芯（3）调节芯的冷却剂流量的方法。

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