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1. 发明授权

US4929412A Control rod 失效
公开(公告)号：US4929412A
公开(公告)日：1990-05-29
申请号：US336941
申请日：1989-04-11
申请人： Robert C. Dixon , James E. Cearley , Paul Van Diemen , Edwin D. Sayre , Gerald M. Gordon
发明人： Robert C. Dixon , James E. Cearley , Paul Van Diemen , Edwin D. Sayre , Gerald M. Gordon
IPC分类号： G21C7/113
CPC分类号： G21C7/113 , G21Y2002/201 , G21Y2002/301 , G21Y2004/30 , Y02E30/39
摘要： An apparatus and process for control rod assembly and construction for a nuclear reactor is disclosed wherein the control rod is of cruciform configuration having a plurality of and preferably four flat planar members. Each planar member is made up with an assembly of square cross sectioned tubular members. Each square cross sectioned tubular member includes a defined cylindrical center and a constant thickness surrounding tubular metallic shell to provide the contained neutron absorbing materials in a cylindrically shaped pressure vessel. The constant thickness surrounding tubular shell constituting the cylindrical shaped pressure vessel has four corner sections added to generate a modified square exterior profile. These added four corner sections comprise an addition to the tubular side wall thickness of the shell. Appropriate chamfers and rounding are provided to the square profile to impart both stress relief and convenient points for automated welding between side-by-side square sections. The square cross sectioned tubular members when welded together extend axially and longitudinally the length of the control rod in the direction of control rod movement and fluid flow. The square cross sectioned tubular members are filled with a neutron absorbing material, plugged at both ends, and fastened by welding in side-by-side relation to form the planar control rod members of the required cruciform shape. These square cross sectioned tubular members as welded in side-by-side relation are in integral portion of the longitudinal support structure of the control rod and fasten and interconnect the handle at the top of the control rod and a conventional velocity limiting device at the bottom of the control rod. The fastening of the handles and velocity limiting device at the respective top and bottom provides a secondary and supplemental seal to primary plugs containing the neutron absorbing material. If needed for enhanced life, provision is made for the incorporation of a hafnium plate in a rectangular sectioned tube adjacent the handle at upper end of the control rod, this tip being variable in length dependent upon individual control rod requirements. Thus square sectioned tubular members form an improved poison containing cylindrical volume for providing resultant improved control rod worth and increased in service life time in moderating and shutting down nuclear reactions. Consequently, the disclosed construction can be used both for conventional control rods as well as for control rod configured for control cell locations.

2. 发明授权

US4902470A Control rod 失效
标题翻译：控制杆
公开(公告)号：US4902470A
公开(公告)日：1990-02-20
申请号：US31633
申请日：1987-03-30
申请人： Robert C. Dixon , James E. Cearley , Paul Van Diemen , Edwin D. Sayre , Gerald M. Gordon
发明人： Robert C. Dixon , James E. Cearley , Paul Van Diemen , Edwin D. Sayre , Gerald M. Gordon
IPC分类号： G21C7/113
CPC分类号： G21C7/113 , G21Y2002/201 , G21Y2002/301 , G21Y2004/30 , Y02E30/39
摘要： An apparatus and process for control rod assembly and construction for a nuclear reactor is disclosed wherein the control rod is of cruciform configuration having a plurality of and preferably four flat planar members. Each planar member is made up with an assembly of square cross sectioned tubular members. Each square cross sectioned tubular member includes a defined cylindrical center and a constant thickness surrounding tubular metallic shell to provide the contained neutron absorbing materials in a cylindrically shaped pressure vessel. The constant thickness surrounding tubular shell constituting the cylindrical shaped pressure vessel has four corner sections added to generate a modified square exterior profile. These added four corner sections comprise an addition to the tubular side wall thickness of the shell. Appropriate chamfers and rounding are provided to the square profile to impart both stress relief and convenient points for automated welding between side-by-side square sections. The square cross sectioned tubular members when welded together extend axially and longitudinally the length of the control rod in the direction of control rod movement and fluid flow. The square cross sectioned tubular members are filled with a neutron absorbing material, plugged at both ends, and fastened by welding in side-by-side relation to form the planar control rod members of the required cruciform shape. These square cross sectioned tubular members as welded in side-by-side relation are an integral portion of the longitudinal support structure of the control rod and fasten and interconnect the handle at the top of the control rod and a conventional velocity limiting device at the bottom of the control rod. The fastening of the handles and velocity limiting device at the respective top and bottom provides a secondary and supplemental seal to primary plugs containing the neutron absorbing material. If needed for enhanced life, provision is made for the incorporation of a hafnium plate in a rectangular sectioned tube adjacent the handle at upper end of the control rod, this tip being variable in length dependent upon individual control rod requirements. Thus square sectioned tubular members form an improved poison containing cylindrical volume for providing resultant improved control rod worth and increased in service life time in moderating and shutting down nuclear reactions. Consequently, the disclosed construction can be used both for conventional control rods as well as for control rod configured for control cell locations.

3. 发明授权

US07206372B2 Methods of repairing leaking elongate hollow members in boiling water reactors 有权
标题翻译：在沸水反应堆中修复泄漏的细长型中空构件的方法
公开(公告)号：US07206372B2
公开(公告)日：2007-04-17
申请号：US10845318
申请日：2004-05-14
申请人： Eric R. Willis , Sampath Ranganath , Paul Van Diemen
发明人： Eric R. Willis , Sampath Ranganath , Paul Van Diemen
IPC分类号： G21C19/00
CPC分类号： G21C13/036 , F16L5/022 , G21C17/017 , G21Y2002/201 , G21Y2002/202 , G21Y2002/204 , G21Y2002/40 , G21Y2002/50 , G21Y2004/40 , G21Y2004/504 , Y02E30/40
摘要： In a method for sealing a hollow, elongate member within a reactor pressure vessel of a nuclear reactor, a section of the elongate member may be removed to separate the elongate member into an upper portion and a lower portion with an opening there between. The lower portion may be attached to a surface of the reactor pressure vessel in-situ, so as to seal off a potential leakage path through the elongate member.
摘要翻译：在用于在核反应堆的反应堆压力容器内密封中空细长构件的方法中，可以移除细长构件的一部分以将细长构件分离成上部和下部，其间具有开口。下部可以原位附接到反应堆压力容器的表面，以便密封通过细长构件的潜在泄漏路径。

4. 发明授权

US4882123A Hafnium control rod for nuclear reactors 失效
标题翻译：用于核反应堆的铪控制棒
公开(公告)号：US4882123A
公开(公告)日：1989-11-21
申请号：US162449
申请日：1988-03-01
申请人： James E. Cearley , David A. Salmon , Paul Van Diemen
发明人： James E. Cearley , David A. Salmon , Paul Van Diemen
IPC分类号： G21C7/10 , G21C7/113 , G21C7/24
CPC分类号： G21C7/113 , G21Y2002/201 , G21Y2004/10 , G21Y2004/30 , Y02E30/39
摘要： A neutron absorbing control device for service in nuclear reactors utilizing fissionable fuel. The control device includes hafnium metal as the neutron absorbing material which is employed in a unique structure which maximizes the advantages of hafnium while minimizing its disadvantages as well as providing other benefits.

5. 发明授权

US06834092B2 Method of repairing leaking elongate hollow members in boiling water reactors 失效
标题翻译：在沸水反应堆中修复泄漏的细长型中空构件的方法
公开(公告)号：US06834092B2
公开(公告)日：2004-12-21
申请号：US10193992
申请日：2002-07-15
申请人： Eric R. Willis , Sampath Ranganath , Paul Van Diemen
发明人： Eric R. Willis , Sampath Ranganath , Paul Van Diemen
IPC分类号： G21C13028
CPC分类号： G21C13/036 , G21C17/017 , G21Y2002/201 , G21Y2002/202 , G21Y2002/40 , G21Y2004/40 , G21Y2004/504 , Y02E30/40 , Y10T29/49728
摘要： The method facilitates sealing a control rod drive (CRD) housing to a stub tube in a reactor pressure vessel of a nuclear reactor, if any cracks develop proximate a heat affected zone of the stub tube at a CRD housing re-attachment weld. The method includes cutting the CRD housing to separate an upper portion of the CRD housing from a lower portion of the CRD housing. The lower portion remains in place and in substantial alignment with the upper portion of the CRD housing. A lower portion member, which may be the lower portion that was cut, is re-attached to the reactor vessel by a re-attachment weld at a location below potential differential leakage paths along the CRD housing. The heat affected zone (e.g., at the re-attachment weld) is covered with a corrosion resistant material to prevent future leaking, and to protect the weld from inter-granular stress corrosion cracking (IGSCC).
摘要翻译：该方法有助于将控制棒驱动器（CRD）壳体密封到核反应堆的反应堆压力容器中的短管，如果在CRD壳体重新附接焊缝处附近存在裂纹发生在短截线管的热影响区域附近。该方法包括切割CRD壳体以将CRD壳体的上部与CRD壳体的下部分离。下部保持在适当位置并且与CRD壳体的上部基本对准。下部部件，其可以是被切割的下部，通过在沿着CRD壳体的潜在的差动泄漏路径下方的位置处的再附着焊接被重新附接到反应堆容器。热影响区域（例如，在再附着焊接处）被覆盖有耐腐蚀材料以防止将来泄漏，并保护焊缝免受颗粒间应力腐蚀开裂（IGSCC）的影响。

6. 发明授权

US4992225A Water corrosion-resistant ceramic oxide body 失效
标题翻译：耐水腐蚀陶瓷氧化物体
公开(公告)号：US4992225A
公开(公告)日：1991-02-12
申请号：US260211
申请日：1988-10-19
申请人： Paul Van Diemen , Kenneth W. Lay
发明人： Paul Van Diemen , Kenneth W. Lay
IPC分类号： C04B35/50 , C04B35/51 , G21C7/24
CPC分类号： G21C7/24 , C04B35/50 , Y02E30/39
摘要： A lanthanide oxide selected from the group consisting of dysprosium oxide, erbium oxide, europium oxide, gadolium oxide and samarium oxide is formed into a compact and sintered to produce a body useful as a control rod material in a water cooled nuclear reactor. The lanthanide oxide is preferably combined with a corrosion stabilizing group 4A metal oxide such as hafnium oxide.
摘要翻译：将选自氧化镝，氧化铒，氧化铕，氧化钆和氧化钐的镧系元素氧化物形成为紧凑型并烧结，以制造用作水冷核反应堆中的控制棒材料的主体。镧系元素氧化物优选与腐蚀稳定基团4A的金属氧化物如氧化铪组合。

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