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公开(公告)号：US4879090A
公开(公告)日：1989-11-07
申请号：US88439
申请日：1987-08-24
申请人： Patrick A. Perrotti , Paul F. Joffre , Zeses E. Karoutas , Lawrence V. Corsetti , William J. Bryan , Stephen C. Hatfield
发明人： Patrick A. Perrotti , Paul F. Joffre , Zeses E. Karoutas , Lawrence V. Corsetti , William J. Bryan , Stephen C. Hatfield
CPC分类号： G21C3/322 , G21C3/3563 , G21Y2002/201 , G21Y2002/303 , G21Y2004/30 , G21Y2004/302 , Y02E30/38
摘要： Integral vanes 4 with optimized size, shape and bend angles maximize coolant mixing and fuel rod 12 heat transfer downstream. Recessed weld nuggets 5 with no vane cutout are optimized for size, strength and corrosion resistance. Staggered arches 20',22' and springs 20,22 minimize turbulence and reduce grid pressure drop and promote coolant mixing. Crowned arches 20',22' and springs 20,22 decrease scoring of fuel rods 12 and are sized to minimize turbulence and pressure drop. Minimum cutouts in unslotted section of grid strip 46,46' give 15-20% strength increase. Intermediate weld and tapered end slots 48 give 15% strength increase. Ribbed and round dimple stiffeners 38,39 on outer strips increase buckling resistance, reduce handling damage and spreads accidental loading. Outer strips 32 are optimized for strength, handling, turbulence generation and pressure drop. They also divert enough flow to interior of fuel assembly to match thermal power distribution and eliminate fuel rod corrosion concerns.
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2.发明授权
公开(公告)号：US5227129A
公开(公告)日：1993-07-13
申请号：US960268
申请日：1992-10-13
CPC分类号： G21C3/07 , C23C14/0641 , C23C14/325 , Y02E30/40
摘要： A corrosion resistant metallic coating (60) of zirconium nitride is applied to the cladding tube (40) of a nuclear fuel rod (20). The zirconium nitride is reactively deposited on a zirconium-alloy cladding tube by a cathodic arc plasma deposition process. The zirconium nitride coating provides superior wear test results and enhances the corrosion resistance of the cladding tube.
摘要翻译： 将氮化锆的耐腐蚀金属涂层（60）施加到核燃料棒（20）的包层管（40）上。 氮化锆通过阴极电弧等离子体沉积工艺反应沉积在锆合金包层管上。 氮化锆涂层提供了优异的耐磨试验结果，并提高了包层管的耐腐蚀性。
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公开(公告)号：US5317612A
公开(公告)日：1994-05-31
申请号：US950590
申请日：1992-09-25
CPC分类号： G21C3/18 , G21Y2002/206 , G21Y2004/101 , G21Y2004/304 , Y02E30/40
摘要： A composite holddown spring for applying an axial force to a fuel pellet stack in a nuclear reactor fuel rod. The composite holddown spring comprises a shape-memory alloy spring portion and a conventional metal spring portion. The shape-memory alloy spring portion has a two-way memory characteristic such that it contracts to a low temperature configuration at ambient temperatures wherein the axial force exerted by the shape-memory alloy spring portion is minimized and expands to a high temperature configuration at operating conditions wherein the axial force exerted by the shape-memory alloy spring portion is maximized. Somewhat conversely, the conventional metal spring portion weakens and contracts at operating temperature and strengthens and expands at atmospheric temperature.
摘要翻译： 一种用于向核反应堆燃料棒中的燃料芯块堆施加轴向力的复合压紧弹簧。 复合压紧弹簧包括形状记忆合金弹簧部分和传统的金属弹簧部分。 形状记忆合金弹簧部分具有双向记忆特性，使得其在环境温度下收缩到低温构造，其中由形状记忆合金弹簧部分施加的轴向力最小化并且在操作时扩展到高温构造 由形状记忆合金弹簧部分施加的轴向力最大化的条件。 相反地，传统的金属弹簧部分在工作温度下变弱并收缩，并在大气温度下增强和膨胀。
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公开(公告)号：US5267290A
公开(公告)日：1993-11-30
申请号：US906379
申请日：1992-06-30
CPC分类号： G21C3/18 , C22C16/00 , C22F1/18 , G21C3/07 , G21C7/04 , G21Y2002/103 , G21Y2002/104 , G21Y2004/101 , Y02E30/40
摘要： A burnable-absorber-containing zirconium alloy is described for application to the inside surface of cladding tubes for light water nuclear reactors. The alloy comprises naturally occurring erbium in a range from a measurable amount up to about 20 wt. % or isotopically purified erbium-167 in a range from a measurable amount up to about 5 wt. %; tin in a range from a measurable amount up to about 0.5 wt. %; iron in a range from a measurable amount up to about 0.2 wt. %; chromium in a range from a measurable amount up to about 0.1 wt. %; niobium in a range from a measurable amount up to about 0.1 wt. %; silicon in a range from about 50 to about 120 parts per million ("ppm"); oxygen in a range from a measurable amount up to about 800 ppm; and the balance zirconium. Such an alloy provides an effective absorber material for reactor control, while providing adequate mechanical properties and corrosion resistance for the intended application.
摘要翻译： 描述了含可燃吸收剂的锆合金用于轻水核反应堆的包覆管的内表面。 该合金包括天然存在的铒，其范围可测量至多约20wt。 ％或同位素纯化的铒-167在可测量至多约5重量％的范围内。 ％; 锡在可测量的范围内至多约0.5重量％ ％; 铁在可测量的范围内至多约0.2重量％ ％; 在可测量的范围内的铬至约0.1重量％ ％; 铌在可测量至约0.1重量％的范围内。 ％; 在约50至约120ppm（“ppm”）范围内的硅; 在可测量的范围内的氧至约800ppm; 余量为锆。 这种合金提供了用于反应器控制的有效的吸收材料，同时为预期应用提供足够的机械性能和耐腐蚀性。
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公开(公告)号：US5241571A
公开(公告)日：1993-08-31
申请号：US906357
申请日：1992-06-30
摘要： A burnable absorber controls axial power peaking or moderator temperature coefficient while additional elements are added to improve strength and/or corrosion resistance in a zirconium alloy containing erbium in a range of from about 0.05 to 2 wt. % selected from the group consisting of a naturally occurring distribution of isotopically enriched erbium-167 and a combination thereof; in a range of from a measurable amount up to 1.4% tin; from 0.2 to 0.5 wt. % iron; from 0.07 to 0.25 wt. % chromium; in a range of from a measurable amount up to 0.6 wt. % niobium; in a range of from a measurable amount up to 0.5 wt. % vanadium; 50-120 ppm silicon; 1000-2200 ppm oxygen and a balance of zirconium. Alternatively, the erbium can be replaced by gadolinium in a range of from about 0.05 to 6 wt. % selected from the group consisting of a naturally occurring distribution of gadolinium isotopes, isotopically enriched gadolinium-157 and a combination thereof.
摘要翻译： 可燃性吸收器控制轴向功率峰值或调节剂温度系数，同时添加另外的元素以提高在约0.05至2重量％范围内的含有铒的锆合金中的强度和/或耐腐蚀性。 ％选自由天然存在的同位素富集的铒-167的分布及其组合组成的组; 在可测量的范围内，锡达到1.4％ 0.2至0.5wt。 铁％ 0.07至0.25wt。 ％铬; 在可测量至0.6重量％的范围内。 ％铌; 在可测量的量至0.5重量％的范围内。 ％钒 50-120ppm硅; 1000-2200ppm氧气和余量的锆。 或者，铒可以由约0.05至6重量％的范围内的钆代替。 ％选自由天然存在的钆同位素分布，同位素富集的钆-157及其组合组成的组。
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