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1. 发明授权

US08116422B2 LWR flow channel with reduced susceptibility to deformation and control blade interference under exposure to neutron radiation and corrosion fields 有权
标题翻译： LWR流道在暴露于中子辐射和腐蚀场的同时降低了对变形的敏感性和控制叶片的干扰
公开(公告)号：US08116422B2
公开(公告)日：2012-02-14
申请号：US11320477
申请日：2005-12-29
申请人： Daniel Reese Lutz , Gerald Allen Potts , Yang-Pi Lin , Sheikh Tahir Mahmood , Mark Andrew Dubecky , David William White , John Schardt
发明人： Daniel Reese Lutz , Gerald Allen Potts , Yang-Pi Lin , Sheikh Tahir Mahmood , Mark Andrew Dubecky , David William White , John Schardt
IPC分类号： G21C9/00 , G21C7/10
CPC分类号： G21C3/07 , G21C3/324 , G21Y2002/203 , G21Y2002/207 , G21Y2004/10 , G21Y2004/201 , Y02E30/40
摘要： A zirconium alloy suitable for forming reactor components that exhibit reduced irradiation growth and improved corrosion resistance during operation of a light water reactor (LWR), for example, a boiling water reactor (BWR). During operation of the reactor, the reactor components will be exposed to a strong, and frequently asymmetrical, radiation fields sufficient to induce or accelerate corrosion of the irradiated alloy surfaces within the reactor core. Reactor components fabricated from the disclosed zirconium alloy will also tend to exhibit an improved tolerance for cold-working during fabrication of the component, thereby simplifying the fabrication of such components by reducing or eliminating subsequent thermal processing, for example, anneals, without unduly degrading the performance of the finished component.
摘要翻译：适用于形成反应器组分的锆合金，其在轻水反应器（LWR），例如沸水反应器（BWR）的操作期间表现出减少的照射生长和改善的耐腐蚀性。在反应器的操作期间，反应器部件将暴露于足以引起或加速反应堆堆芯内辐射的合金表面的腐蚀的强烈且常常不对称的辐射场。由公开的锆合金制造的反应器部件也将倾向于在部件制造期间显示出对冷加工的改善的公差，从而通过减少或消除随后的热处理（例如退火）来简化这些部件的制造，而不会不适当地降低成品组件的性能。

2. 发明申请

US20110180184A1 SURFACE LASER TREATMENT OF ZR-ALLOY FUEL BUNDLE MATERIAL 审中-公开
标题翻译： ZR合金燃料组件材料表面激光处理
公开(公告)号：US20110180184A1
公开(公告)日：2011-07-28
申请号：US11611348
申请日：2006-12-15
申请人： Daniel Reese Lutz , Yang-Pi Lin , Gerald Potts , William H. Jackson
发明人： Daniel Reese Lutz , Yang-Pi Lin , Gerald Potts , William H. Jackson
IPC分类号： C23C8/00 , G21C3/07 , B23K26/00
CPC分类号： G21C21/02 , C22F1/186 , G21C3/32
摘要： A method for treating a Zr-alloy fuel bundle material in a nuclear reactor includes treating a surface of the Zr-alloy fuel bundle material with a laser beam generated by a solid-state laser, and a nuclear reactor including a treated Zr-alloy fuel bundle material. This may reduce the generation of shadow corrosion and/or reduce the propensity for interference between control blade and fuel channel during operation of the nuclear reactor.
摘要翻译：一种用于处理核反应堆中的Zr合金燃料束材料的方法，包括用固体激光器产生的激光束对Zr合金燃料束材料的表面进行处理，以及包括经处理的Zr合金燃料束材料。这可以减少在核反应堆运行期间阴影腐蚀的产生和/或降低控制叶片与燃料通道之间干扰的倾向。

3. 发明申请

US20120033779A1 METHODS OF DETERMINING IN-REACTOR SUSCEPTIBILITY OF A ZIRCONIUM-BASED ALLOY TO SHADOW CORROSION 审中-公开
标题翻译：确定基于锆的合金的腐蚀反应物的腐蚀性的方法
公开(公告)号：US20120033779A1
公开(公告)日：2012-02-09
申请号：US12850244
申请日：2010-08-04
申请人： Daniel Reese Lutz , Young Jin Kim , Yang-Pi Lin
发明人： Daniel Reese Lutz , Young Jin Kim , Yang-Pi Lin
IPC分类号： G21C17/00
CPC分类号： G21C17/06 , G01N17/04 , G21C17/00
摘要： A method of determining in-reactor susceptibility of a zirconium-based alloy to shadow corrosion according to a non-limiting embodiment of the present invention may include immersing a first electrode and a second electrode in an electrolytic solution. The first electrode may be formed of the zirconium-based alloy, while the second electrode may be formed of a metallic material suitable for use in a nuclear reactor and having a higher electrochemical corrosion potential than the zirconium-based alloy. The method may additionally include irradiating the immersed first and second electrodes with electromagnetic radiation. A galvanic current may then be measured between the first electrode and the second electrode to ascertain the relative in-reactor susceptibility of the zirconium-based alloy to shadow corrosion. The present invention allows a simplified and more rapid method of developing solutions that mitigate shadow corrosion, thereby potentially saving years of expensive in-reactor testing.
摘要翻译：根据本发明的非限制性实施例，确定锆基合金对阴影腐蚀的反应器内易感性的方法可以包括将第一电极和第二电极浸入电解液中。第一电极可以由锆基合金形成，而第二电极可以由适于在核反应堆中使用并且具有比锆基合金更高的电化学腐蚀电位的金属材料形成。该方法可以另外包括用电磁辐射照射浸没的第一和第二电极。然后可以在第一电极和第二电极之间测量电流，以确定锆基合金相对于反应器内的易受影响的腐蚀。本发明允许简化和更快速的开发解决方案的方法，其减轻阴影腐蚀，从而潜在地节省了数年的昂贵的反应堆内测试。

4. 发明申请

US20090252280A1 Detachable nuclear reactor fuel assembly component 失效
标题翻译：可拆卸核反应堆燃料组件组件
公开(公告)号：US20090252280A1
公开(公告)日：2009-10-08
申请号：US12078904
申请日：2008-04-08
申请人： Daniel Reese Lutz
发明人： Daniel Reese Lutz
IPC分类号： G21C3/32
CPC分类号： G21C3/04 , G21C3/326 , Y02E30/38
摘要： Example embodiments are directed to fuel assembly components and nuclear fuel bundles including the fuel assembly components. Example embodiments of a fuel assembly component may include a cylindrical device having first and second ends and a mounting assembly on the first end of the cylindrical device configured to attach to and detach from a partial length fuel rod. Example embodiments of a nuclear fuel bundle may include an upper tie plate, a lower tie plate, at least one full-length fuel rod, at least one partial length fuel rod, and a fuel assembly component.
摘要翻译：示例性实施例涉及包括燃料组件部件的燃料组件部件和核燃料束。燃料组件部件的示例性实施例可以包括具有第一端和第二端的圆柱形装置和在圆柱形装置的第一端上的安装组件，其被配置为附接到部分长度的燃料棒并从其分离。核燃料束的示例性实施例可以包括上连接板，下连接板，至少一个全长燃料棒，至少一个部分长度燃料棒和燃料组件部件。

5. 发明授权

US06243433B1 Cladding for use in nuclear reactors having improved resistance to stress corrosion cracking and corrosion 有权
公开(公告)号：US06243433B1
公开(公告)日：2001-06-05
申请号：US09312021
申请日：1999-05-14
申请人： Ronald Bert Adamson , Daniel Reese Lutz , Mickey Orville Marlowe , John Frederick Schardt , Cedric David Williams
发明人： Ronald Bert Adamson , Daniel Reese Lutz , Mickey Orville Marlowe , John Frederick Schardt , Cedric David Williams
IPC分类号： G21C307
CPC分类号： G21C3/20 , G21C3/07 , G21Y2002/103 , G21Y2002/104 , G21Y2004/10 , G21Y2004/20 , Y02E30/40
摘要： An improved fuel element for use in a nuclear reactor comprised of a central core of nuclear material, which is surrounded by a composite cladding. The cladding has an outer metallic tubular portion comprised of well-known cladding alloys used for such purposes. Metallurgically bonded to the outer metallic tubular portion is a commercially pure zirconium microalloyed with a controlled quantity of iron. The zirconium microalloyed with iron produced an inner metallic barrier having a beneficial balance between stress corrosion crack resistance and corrosion resistance while retaining other beneficial properties of pure zirconium, such as ductility.

6. 发明授权

US08565367B2 Detachable nuclear reactor fuel assembly component 失效
公开(公告)号：US08565367B2
公开(公告)日：2013-10-22
申请号：US12078904
申请日：2008-04-08
申请人： Daniel Reese Lutz
发明人： Daniel Reese Lutz
IPC分类号： G21C3/34
CPC分类号： G21C3/04 , G21C3/326 , Y02E30/38
摘要： Example embodiments are directed to fuel assembly components and nuclear fuel bundles including the fuel assembly components. Example embodiments of a fuel assembly component may include a cylindrical device having first and second ends and a mounting assembly on the first end of the cylindrical device configured to attach to and detach from a partial length fuel rod. Example embodiments of a nuclear fuel bundle may include an upper tie plate, a lower tie plate, at least one full-length fuel rod, at least one partial length fuel rod, and a fuel assembly component.

7. 发明授权

US06542566B2 Cladding for use in nuclear reactors having improved resistance to stress corrosion cracking and corrosion 有权
标题翻译：用于核反应堆的包层具有改善的耐应力腐蚀开裂和腐蚀性能
公开(公告)号：US06542566B2
公开(公告)日：2003-04-01
申请号：US09801364
申请日：2001-03-07
申请人： Ronald Bert Adamson , Daniel Reese Lutz , Mickey Orville Marlowe , John Frederick Schardt , Cedric David Williams
发明人： Ronald Bert Adamson , Daniel Reese Lutz , Mickey Orville Marlowe , John Frederick Schardt , Cedric David Williams
IPC分类号： G21C300
CPC分类号： G21C3/20 , G21C3/07 , G21Y2002/103 , G21Y2002/104 , G21Y2004/10 , G21Y2004/20 , Y02E30/40
摘要： An improved fuel element for use in a nuclear reactor comprised of a central core of nuclear material, which is surrounded by a composite cladding. The cladding has an outer metallic tubular portion comprised of well-known cladding alloys used for such purposes. Metallurgically bonded to the outer metallic tubular portion is a commercially pure zirconium microalloyed with a controlled quantity of iron. The zirconium microalloyed with iron produced an inner metallic barrier having a beneficial balance between stress corrosion crack resistance and corrosion resistance while retaining other beneficial properties of pure zirconium, such as ductility.
摘要翻译：用于核反应堆的改进的燃料元件，其由核材料的中心核心组成，其被复合包层包围。包层具有由用于这些目的的众所周知的包层合金构成的外部金属管状部分。与外部金属管状部分冶金结合的是商业上纯的与受控量铁合金化的锆。与铁微合金的锆产生了内部金属屏障，其在应力腐蚀开裂性和耐腐蚀性之间具有有利的平衡，同时保留了纯锆的其它有益性质，例如延展性。

8. 发明授权

US5703371A Modified notched energy filter neutron radiography camera for non-destructive determination of hydrogen content of irradiated BWR fuel elements 失效
标题翻译：改进的缺口能量过滤器中子射线照相机用于无损测定辐射BWR燃料元素的氢含量
公开(公告)号：US5703371A
公开(公告)日：1997-12-30
申请号：US689565
申请日：1996-08-12
申请人： David Michael Farkas , Daniel Reese Lutz
发明人： David Michael Farkas , Daniel Reese Lutz
IPC分类号： G01N23/05 , G01N23/204 , G01N23/202
CPC分类号： G01N23/05
摘要： A neutron radiography camera operates in cooperation with a neutron beam source for determining hydrogen content of irradiated BWR fuel elements. The camera implements the method using a notched neutron spectrum filter to determine the hydrogen content. The camera is specifically configured to take advantage of the tubular geometry of a nuclear fuel rod. Incident neutron beam ports are formed in a base unit that receives an incident filtered neutron beam. The ports aim the neutron beam at a periphery of the BWR fuel elements, which in the context of nuclear fuel rods includes zirconium alloy cladding. Collision of the neutrons with hydrogen in the cladding lowers their energy and scatters them at preferential angles. Scatter cavities defining scattered neutron paths are formed in the base unit, and absorber plates are disposed of terminal ends of the scatter cavities. The absorber plates become activated by resonance absorption from the neutrons scattered by hydrogen in the target fuel elements. The hydrogen content can be determined from the activated absorber plates.
摘要翻译：中子射线摄影照相机与中子束源协同工作，以确定照射的BWR燃料元件的氢含量。相机使用缺口中子频谱滤波器来实现该方法来确定氢含量。相机被特别地配置成利用核燃料棒的管状几何形状。事件中子束端口形成在接收入射过滤的中子束的基本单元中。这些端口将中子束瞄准BWR燃料元件的周边，在核燃料棒的上下文中包括锆合金包层。包层中的中子与氢的碰撞降低了它们的能量，并以优先的角度散射它们。形成分散中子路径的散射腔形成在基座单元中，并且吸收板设置在散射空腔的末端。吸收板通过来自目标燃料元件中由氢分散的中子的共振吸收而激活。可以从活化的吸收板确定氢含量。

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