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1. 发明授权

US4692302A Coolant flow mixer grid for a nuclear reactor fuel assembly 失效
标题翻译：用于核反应堆燃料组件的冷却剂流动混合器格栅
公开(公告)号：US4692302A
公开(公告)日：1987-09-08
申请号：US567450
申请日：1983-12-30
申请人： Edmund E. DeMario , Raymond F. Boyle , Peter J. Kuchirka
发明人： Edmund E. DeMario , Raymond F. Boyle , Peter J. Kuchirka
IPC分类号： G21C3/322 , G21C3/34 , G21C3/356
CPC分类号： G21C3/3563 , G21C3/322 , G21C2003/3432 , G21Y2002/201 , G21Y2002/303 , G21Y2004/30 , G21Y2004/302 , Y02E30/38
摘要： An improved grid structure is provided for a nuclear reactor fuel assembly whose sole purpose is to promote a crossflow mixing of the coolant through the fuel assembly rather than the support of the fuel rods. The grid straps form an egg-crate configuration creating cell openings for receiving the fuel rods. Associated with each cell opening is at least one coolant flow mixing vane that projects over the cell opening and four dimple protrusions which are open to the flow of coolant therethrough. The dimple protrusions extend into the cell opening to a further extent than the mixing vane so as to prevent damaging impact of the fuel rod with a vane upon transverse movement of the fuel rod across the cell opening. In reducing the pressure drop of the coolant flow through the assembly, the height of the inner grid straps is substantially less than the height of the outer border strap.
摘要翻译：为核反应堆燃料组件提供了改进的格栅结构，其单一目的是促进冷却剂通过燃料组件的交叉流混合，而不是燃料棒的支撑。网格带形成蛋箱配置，创建用于接收燃料棒的电池开口。与每个电池开口相关联的是至少一个冷却剂流动混合叶片，其突出在电池开口和四个凹部突出部分之间，这些突起部通过其中的冷却剂流动开放。凹坑突起延伸到电池开口中比混合叶片更大程度地延伸，以便防止燃料棒在燃料棒穿过电池开口的横向运动时对叶片的燃料棒的冲击。在减少通过组件的冷却剂流的压降中，内网格带的高度实质上小于外边界带的高度。

2. 发明授权

US4279700A Tritium removal and retention device 失效
标题翻译：氚去除和保留装置
公开(公告)号：US4279700A
公开(公告)日：1981-07-21
申请号：US950359
申请日：1978-10-11
申请人： Raymond F. Boyle , Docile D. Durigon
发明人： Raymond F. Boyle , Docile D. Durigon
IPC分类号： G21C3/17 , G21C3/02
CPC分类号： G21C3/17 , Y02E30/40
摘要： Apparatus comprising a two layered composite with an internal core of zirconium or zirconium alloy which retains tritium, and an adherent nickel outer layer which acts as a protective and selective window for passage of the tritium.
摘要翻译：包括具有保留氚的锆或锆合金的内核的双层复合材料的装置以及用作通过氚的保护性选择性窗口的附着镍外层。

3. 发明授权

US4652426A Water tubes arranged in cross-like pattern in a fuel assembly 失效
标题翻译：在燃料组件中布置成十字形图案的水管
公开(公告)号：US4652426A
公开(公告)日：1987-03-24
申请号：US642844
申请日：1984-08-20
申请人： Raymond F. Boyle , Richard S. Miller , Carl A. Olson
发明人： Raymond F. Boyle , Richard S. Miller , Carl A. Olson
IPC分类号： G21C3/326 , G21C1/04
CPC分类号： G21C3/326 , Y02E30/38
摘要： An improved nuclear fuel assembly includes a plurality of elongated water tubes arranged in a cross-like pattern spaced among a plurality of fuel rods for providing individual, spaced-apart coolant-moderator water flow paths lengthwise through the assembly. Some of the water tubes also function as tie rods interconnecting upper and lower tie plates of the fuel assembly.
摘要翻译：改进的核燃料组件包括多个细长的水管，其布置成在多个燃料棒之间间隔开的十字形图案，用于在整个组件中纵向提供单独的间隔开的冷却剂 - 调节剂水流径。一些水管还用作连接燃料组件的上下连接板的拉杆。

4. 发明授权

US4636352A Nuclear fuel rod with burnable plate and pellet-clad interaction fix 失效
标题翻译：具有可燃板和颗粒包层相互作用固定的核燃料棒
公开(公告)号：US4636352A
公开(公告)日：1987-01-13
申请号：US578336
申请日：1984-02-09
申请人： Raymond F. Boyle
发明人： Raymond F. Boyle
IPC分类号： G21C3/28 , G21C3/17 , G21C3/18 , G21C7/04 , G21C3/00
CPC分类号： G21C3/18 , G21C7/04 , G21Y2002/104 , G21Y2004/10 , G21Y2004/30 , Y02E30/39
摘要： An improved nuclear fuel rod comprising a tubular metallic cladding containing a plurality of nuclear fuel pellets has a plurality of ceramic wafers therein, each of which wafers being disposed between a major portion of adjacent fuel pellets. The ceramic wafers are formed from a sintered mixture of natural or depleted uranium dioxide and 1-8 percent by weight gadolinium oxide. The wafers are of a diameter substantially the same as that of the fuel pellets and have a thickness of between 10-100 mils. The wafers freeze out harmful fission products released by the fuel pellets and minimize or prevent pellet-clad interaction failures, while also providing flexibility in power shaping in the reactor system.
摘要翻译：包括含有多个核燃料颗粒的管状金属包层的改进的核燃料棒在其中具有多个陶瓷晶片，其中每个晶片布置在相邻燃料颗粒的主要部分之间。陶瓷晶片由天然或贫二氧化铀和1-8重量％的氧化钆的烧结混合物形成。晶片的直径基本上与燃料颗粒的直径相同，并且具有在10-100密耳之间的厚度。晶片可以冻结燃料颗粒释放的有害裂变产物，并最大限度地减少或防止颗粒包层相互作用的故障，同时也提供反应堆系统功率整形的灵活性。

5. 发明授权

US4675153A Zirconium alloy fuel cladding resistant to PCI crack propagation 失效
标题翻译：锆合金燃料包层抗PCI裂纹扩展
公开(公告)号：US4675153A
公开(公告)日：1987-06-23
申请号：US589390
申请日：1984-03-14
申请人： Raymond F. Boyle , John P. Foster
发明人： Raymond F. Boyle , John P. Foster
IPC分类号： B32B15/01 , C22F1/18 , G21C3/20 , G21C3/00
CPC分类号： C22F1/186 , B32B15/01 , G21C3/20 , G21Y2002/103 , G21Y2002/104 , G21Y2002/303 , G21Y2004/10 , Y02E30/40
摘要： Described herein is a composite nuclear fuel rod cladding tube which includes two concentric layers of zirconium base alloys metallurgically bonded to each other. The outer layer is composed of a conventional zirconium base alloy having high strength and excellent aqueous corrosion resistance. The inner layer is composed of a second zirconium base alloy containing about 0.2 to 0.6 wt. % tin, about 0.03 to 0.11 wt. % iron and up to about 350 ppm oxygen. This second alloy while also having excellent aqueous corrosion resistance, is further characterized by the ability to prevent the propagation of cracks initiated during reactor operation due to pellet-cladding interaction.
摘要翻译：这里描述的是一种复合核燃料棒包覆管，其包括彼此冶金结合的两个锆基合金的同心层。外层由具有高强度和优异的耐水腐蚀性的常规锆基合金构成。内层由含有约0.2〜0.6重量％的第二锆基合金构成。％锡，约0.03至0.11wt。％铁和高达约350ppm的氧气。该第二种合金同时具有优异的耐水腐蚀性，其特征还在于防止由于颗粒 - 包层相互作用而在反应器操作过程中引起的裂纹扩展的能力。

6. 发明授权

US4664881A Zirconium base fuel cladding resistant to PCI crack propagation 失效
标题翻译：锆基燃料包层抗PCI裂纹扩展
公开(公告)号：US4664881A
公开(公告)日：1987-05-12
申请号：US589300
申请日：1984-03-14
申请人： Harry M. Ferrari , Raymond F. Boyle , Fred D. Kingsbury, Jr.
发明人： Harry M. Ferrari , Raymond F. Boyle , Fred D. Kingsbury, Jr.
IPC分类号： C22C16/00 , C22F1/18 , G21C3/20 , G21C3/00
CPC分类号： G21C3/20 , C22C16/00 , C22F1/186 , G21Y2002/104 , G21Y2002/206 , G21Y2002/303 , G21Y2004/10 , G21Y2004/201 , G21Y2004/202 , Y02E30/40
摘要： The present invention pertains to zirconium base alloys containing about 0.1 to 0.6 weight percent tin; about 0.07 to 0.24 weight percent iron; about 0.05 to 0.15 weight percent chromium; and up to about 0.05 weight percent nickel. The balance of the alloy is zirconium with incidental impurities. The levels of the incidental impurity, oxygen, is controlled to a level of less than about 350 ppm. These alloys have been designed to minimize the adverse effects of pellet-clad interaction, when they are used as a liner bonded to the inside surface of water reactor nuclear fuel cladding. Specific cladding and fuel element designs according to the present invention are described.
摘要翻译：本发明涉及含有0.1至0.6重量％锡的锆基合金; 约0.07至0.24重量％的铁; 约0.05至0.15重量％的铬; 和最多约0.05重量％的镍。合金的余量是含有杂质的锆。附带杂质，氧气的含量被控制在小于约350ppm的水平。这些合金的设计是为了尽量减少颗粒包层相互作用的不利影响，当它们用作粘结在水反应堆核燃料包层内表面上的衬垫时。描述根据本发明的特定包层和燃料元件设计。

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