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公开(公告)号：US4406012A
公开(公告)日：1983-09-20
申请号：US228344
申请日：1981-01-26
摘要： An improved nuclear fuel element is disclosed for use in the core of nuclear reactors. The improved nuclear fuel element has a composite cladding of an outer portion forming a substrate having on the inside surface a metal layer selected from the group consisting of copper, nickel, iron and alloys of the foregoing with a gap between the composite cladding and the core of nuclear fuel. The nuclear fuel element comprises a container of the elongated composite cladding, a central core of a body of nuclear fuel material disposed in and partially filling the container and forming an internal cavity in the container, an enclosure integrally secured and sealed at each end of said container and a nuclear fuel material retaining means positioned in the cavity. The metal layer of the composite cladding prevents perforations or failures in the cladding substrate from stress corrosion cracking or from fuel pellet-cladding interaction or both. The substrate of the composite cladding is selected from conventional cladding materials and preferably is a zirconium alloy.
摘要翻译： 公开了用于核反应堆核心的改进的核燃料元件。 改进的核燃料元件具有形成衬底的外部部分的复合包层，所述衬底在内表面上具有选自铜，镍，铁的金属层和上述合金与复合材料包层和芯之间的间隙 的核燃料。 核燃料元件包括细长复合包层的容器，核燃料材料体的中心芯，其设置在容器中并部分地填充容器并在容器中形成内腔，外壳在所述容器内的每一端处一体地固定和密封 容器和位于空腔中的核燃料材料保持装置。 复合材料包层的金属层防止包层基体中的应力腐蚀开裂或燃料颗粒 - 包层相互作用或两者的穿孔或失效。 复合包层的基材选自常规包层材料，优选为锆合金。
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公开(公告)号：US4029545A
公开(公告)日：1977-06-14
申请号：US522770
申请日：1974-11-11
摘要： An improved nuclear fuel element is disclosed for use in the core of nuclear reactors. The improved nuclear fuel has a composite cladding container comprising an outer layer having two coatings on the inside surface with the first coating on the outer layer being a diffusion barrier and the second coating on the first coating being a metal layer. The diffusion barrier is comprised of chromium or a chromium alloy, and the metal layer is selected from the group consisting of copper, nickel, iron and alloys thereof. The nuclear fuel element comprises a container of the elongated composite cladding, a central core of a body of nuclear fuel material disposed in and partially filling the container and forming an internal cavity in the container, an enclosure integrally secured and sealed at each end of said container and a nuclear fuel material retaining means positioned in the cavity. The metal layer and the diffusion barrier of the composite cladding prevent perforations or failures in the outer layer of the cladding from stress corrosion cracking or from fuel pellet-cladding interaction or both. The outer layer of the composite cladding is selected from conventional cladding materials and preferably is a zirconium alloy.
摘要翻译： 公开了用于核反应堆核心的改进的核燃料元件。 改进的核燃料具有复合包覆容器，其包括在内表面上具有两个涂层的外层，外层上的第一涂层是扩散阻挡层，第一涂层上的第二涂层是金属层。 扩散阻挡层由铬或铬合金组成，金属层选自铜，镍，铁及其合金。 核燃料元件包括细长复合包层的容器，核燃料材料体的中心芯，其设置在容器中并部分地填充容器并在容器中形成内腔，外壳在所述容器内的每一端处一体地固定和密封 容器和位于空腔中的核燃料材料保持装置。 复合包层的金属层和扩散屏障防止了包层外层的应力腐蚀开裂或燃料颗粒 - 包层相互作用或两者的穿孔或失效。 复合包层的外层选自常规包层材料，优选为锆合金。
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公开(公告)号：US4022662A
公开(公告)日：1977-05-10
申请号：US522771
申请日：1974-11-11
摘要： An improved nuclear fuel element is disclosed for use in the core of nuclear reactors. The improved nuclear fuel element has a metal liner and a diffusion barrier disposed between the cladding and the nuclear fuel material. The diffusion barrier is in the form of a metal coating with the diffusion barrier being coated on the internal surface of the cladding in one embodiment and the diffusion barrier being coated on the outside surface of the metal liner in another embodiment. The diffusion barrier is a coating of chromium or a chromium alloy and serves to prevent any alloying or formation of low melting eutectic liquid phases between the metal liner and the cladding at elevated temperatures. The metal liner is selected from the group consisting of stainless steel, copper, copper alloys, nickel, and nickel alloys.
摘要翻译： 公开了用于核反应堆核心的改进的核燃料元件。 改进的核燃料元件具有设置在包层和核燃料材料之间的金属衬垫和扩散阻挡层。 在一个实施例中，扩散阻挡层是金属涂层的形式，其中扩散阻挡层被涂覆在包层的内表面上，而在另一个实施例中，扩散阻挡层被涂覆在金属衬垫的外表面上。 扩散阻挡层是铬或铬合金的涂层，并且用于在高温下防止在金属衬垫和包层之间的任何合金化或形成低熔点共晶液相。 金属衬套选自不锈钢，铜，铜合金，镍和镍合金。
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4.发明授权Internal passive catalytic ammonia converter for reduction of main steam dose rate associated with hydrogen water chemistry 失效用于降低与氢水化学相关的主蒸汽剂量率的内部被动催化氨转化器
公开(公告)号：US5515406A
公开(公告)日：1996-05-07
申请号：US65964
申请日：1993-05-21
IPC分类号： G21D1/00 , G21C19/317 , G21D3/08
CPC分类号： G21C19/317
摘要： A passive catalytic ammonia converter operating in the water/steam mixture exiting the core of a boiling water reactor. The catalytic ammonia converter is made of catalytic material arranged and situated such that substantially all of the water/steam mixture entering the water/steam separator device flows over the surface of the catalytic material. The catalytic surfaces react ammonia and/or NO with O.sub.2 or H.sub.2 O.sub.2 in the water/steam mixture to form nitrite or nitrate. The passive catalytic ammonia converter is constructed to ensure that the pressure drop of the reactor water across the device is very small. The catalytic ammonia converter can include a plurality of stainless steel flow-through housings packed with catalytic ammonia converter material, which could take the form of tangled wire or strips, crimped ribbon, porous sintered metal composite or any other structure having a high surface area-to-volume ratio.
摘要翻译： 一种被动催化氨转化器，其工作在离开沸水反应堆核心的水/蒸汽混合物中。 催化氨转化器由催化材料制成，催化材料布置和定位，使得进入水/蒸汽分离器装置的基本上所有的水/蒸汽混合物流过催化材料的表面。 催化剂表面在水/蒸汽混合物中将氨和/或NO与O 2或H 2 O 2反应形成亚硝酸盐或硝酸盐。 被动催化氨转化器被构造成确保反应器水在整个装置上的压降非常小。 催化氨转化器可以包括多个不锈钢流通壳体，其中填充有催化氨转化器材料，其可以采取缠结线或条带，卷曲带，多孔烧结金属复合材料或具有高表面积的任何其它结构的形式， 体积比。
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公开(公告)号：US5465278A
公开(公告)日：1995-11-07
申请号：US247736
申请日：1994-05-23
CPC分类号： G21C17/00 , G21C5/10 , G21Y2002/204 , G21Y2004/30 , Y02E30/40
摘要： A method and an apparatus for measuring the degree of intergranular stress corrosion cracking protection in the area of the core shroud weldments. Electrochemical potential sensors are attached to the shroud wall and the upper core spray line at locations near the actual weld surface of concern to ensure the accuracy of the electrochemical potential measurements. A working electrode doped or coated with noble metal and a reference electrode are implanted into the reactor core shroud. A throughhole is drilled or machined into the shroud wall at an elevation just below the top guide support ring, i.e., near the core shroud weldments. Then a plug containing the working and reference electrodes is inserted into the throughhole.
摘要翻译： 一种用于测量核心护套焊件区域中的晶间应力腐蚀开裂保护程度的方法和装置。 电化学电位传感器在靠近实际焊接表面的位置处连接到护罩壁和上芯线喷涂线，以确保电化学电位测量的准确性。 将掺杂或涂覆有贵金属和参考电极的工作电极注入反应堆芯护罩中。 在刚好在顶部导向支撑环下方的高度处，即靠近核心护套焊件，在通孔壁上钻孔或加工通孔。 然后将含有工作电极和参比电极的插头插入到通孔中。
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6.发明授权Method for monitoring noble metal distribution in reactor circuit during plant application 失效在工厂应用中监测电抗器电路中贵金属分布的方法
公开(公告)号：US5625656A
公开(公告)日：1997-04-29
申请号：US482243
申请日：1995-06-07
IPC分类号： B01J37/03 , C23F11/08 , C23F11/18 , G01N17/02 , G21C3/07 , G21C17/02 , G21C17/022 , G21C19/28 , G21C19/30 , G21C19/307
CPC分类号： B01J37/031 , C23F11/08 , C23F11/18 , C23F15/00 , G01N17/02 , G21C17/02 , G21C17/022 , G21C17/0225 , G21C19/28 , G21C19/30 , G21C19/307 , G21C3/07 , G21Y2002/102 , G21Y2002/103 , G21Y2002/104 , G21Y2002/204 , G21Y2004/10 , G21Y2004/20 , G21Y2004/30 , G21Y2004/40 , Y02E30/40
摘要： A method for ensuring the distribution of noble metal in the reactor circuit during plant application without measuring the reactor water for noble metal content by chemical analysis. The method involves the measurement of electrochemical corrosion potential in an autoclave or a high-flow test section that is connected to the reactor water circuit through sample lines downstream of the injection port, preferably the point in the reactor circuit which is furthest from the injection port. If the noble metal flows into the autoclave or test section at these distant points in the reactor circuit, then the noble metal will deposit on the test specimens inside the autoclave or test section. After the noble metal has been injected for a predetermined duration, the electrochemical corrosion potential autoclave or test section is exposed to hydrogen water chemistry conditions and the electrochemical corrosion potentials of the specimens inside the autoclave or test section will be measured to determine the extent of their catalytic response. A good catalytic response indicates that the noble metal has reached the locations upstream where electrochemical corrosion potential is being measured.
摘要翻译： 一种用于确保在植物施用期间在反应器回路中分布贵金属的方法，而不通过化学分析测量贵金属含量的反应器水。 该方法包括在高压灭菌器或高流量测试部分中测量电化学腐蚀电位，该高压灭菌器或高流量试验部分通过注入口下游的取样管线连接到反应器水回路，优选地在反应器电路中与注射端口最远的点 。 如果贵金属在反应器电路中的这些远处流入高压釜或试验部分，则贵金属将沉积在高压釜或试验部分内的试样上。 在将贵金属注入预定时间后，将电化学腐蚀潜力的高压釜或试验部分暴露于氢水化学条件下，并测量高压釜或试验部分内的试样的电化学腐蚀电位，以确定它们的程度 催化反应。 良好的催化反应表明贵金属已经到达测量电化学腐蚀电位的上游位置。
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公开(公告)号：US5608767A
公开(公告)日：1997-03-04
申请号：US505412
申请日：1995-07-21
CPC分类号： C23F13/04 , F04F5/44 , G21C15/25 , G21H1/00 , G21Y2002/201 , G21Y2002/207 , G21Y2004/20 , G21Y2004/30 , G21Y2004/304 , G21Y2004/402 , Y02E30/40
摘要： A device for generating direct current by neutron activation of a plurality of series-connected beta-emitter (nuclear decay electron) cells, located in the out-of-core region of a light water nuclear reactor. The device can be used as either a current source, or preferably configured as a DC voltage source, capable of powering low-power, radiation-hardened, high-temperature integrated circuitry contained in the reactor vessel. As such, the device acts like a DC battery that is activated by (n, .gamma.) reactions, both thermal and epithermal (by resonance capture). The device is not operable until exposed to a substantial neutron flux, so it has unlimited shelf-life and is not radioactive during manufacture In the preferred embodiment, an isotope of the metallic rare-earth element dysprosium is configured in a "sandwich" geometry to generate sufficient current that a useful steady voltage can be generated by means of a simple voltage regulation circuit.
摘要翻译： 一种用于通过中子激活产生直流电的装置，该器件位于轻水核反应堆的芯外区域中的多个串联连接的β-发射体（核衰变电子）单元。 该装置可以用作能够为包含在反应堆容器中的低功率，辐射硬化的高温集成电路供电的电流源或优选地配置为DC电压源。 因此，该装置像通过（n，γ）反应（通过共振捕获）而被激活的直流电池起作用。 该设备在暴露于大量的中子通量之前是不可操作的，因此它具有无限的保质期并且在制造过程中不具有放射性。在优选实施例中，金属稀土元素镝的同位素被构造成“三明治”的几何形状 产生足够的电流，借助于简单的电压调节电路可以产生有用的稳定电压。
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8.发明授权Noble metal doping or coating of crack interior for stress corrosion cracking protection of metals 失效贵金属掺杂或涂层裂纹内部应力腐蚀开裂保护金属
公开(公告)号：US5600691A
公开(公告)日：1997-02-04
申请号：US209572
申请日：1994-03-10
IPC分类号： G21D1/00 , B01J37/03 , C23F11/08 , C23F11/18 , C23F15/00 , G01N17/02 , G21C3/07 , G21C17/02 , G21C17/022 , G21C19/28 , G21C19/30 , G21C19/307 , G21D3/08 , G21C9/00
CPC分类号： G21C17/0225 , B01J37/031 , C23F11/08 , C23F11/18 , C23F15/00 , G01N17/02 , G21C17/02 , G21C19/28 , G21C19/30 , G21C19/307 , G21C3/07 , G21C17/022 , G21Y2002/102 , G21Y2002/103 , G21Y2002/104 , G21Y2002/204 , G21Y2004/10 , G21Y2004/20 , G21Y2004/30 , G21Y2004/40 , Y02E30/40
摘要： A method for mitigating crack growth on the surface of stainless steel or other metal components in a water-cooled nuclear reactor. A compound containing a noble metal, e.g., palladium, is injected into the water of the reactor in the form of a solution or suspension. This compound has the property that it decomposes under reactor thermal conditions to release ions/atoms of the noble metal which incorporate in or deposit on the interior surfaces of the crack. The compound may be organic, organometallic (e.g., palladium acetylacetonate) or inorganic in nature. The palladium deposited inside a crack should exhibit catalytic behavior even if the bulk surface palladium is depleted under high fluid flow conditions. As a result, the electrochemical potential inside the crack is decreased to a level below the critical potential to protect against intergranular stress corrosion cracking.
摘要翻译： 一种减轻水冷核反应堆不锈钢或其他金属部件表面裂纹扩展的方法。 将包含贵金属如钯的化合物以溶液或悬浮液的形式注入反应器的水中。 该化合物具有其在反应器热条件下分解以释放掺入或沉积在裂纹内表面上的贵金属的离子/原子的性质。 化合物可以是有机的，有机金属的（例如乙酰丙酮钯）或无机的。 即使在高流体流动条件下体表面钯耗尽，沉积在裂纹内的钯也应该具有催化作用。 因此，裂纹内部的电化学电位降低到临界电位以下以防止晶间应力腐蚀开裂。
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公开(公告)号：US4017368A
公开(公告)日：1977-04-12
申请号：US522767
申请日：1974-11-11
申请人： Daniel E. Wax , Robert L. Cowan, II
发明人： Daniel E. Wax , Robert L. Cowan, II
CPC分类号： C25D5/38
摘要： A novel aqueous electrolytic activating solution and a method for electroplating zirconium and zirconium alloys are disclosed. The novel aqueous electrolytic activating solution is comprised of from about 10 to about 20 grams per liter of ammonium bifluoride (NH.sub.4 FHF) and from about 0.75 to 2 grams per liter of sulfuric acid (H.sub.2 SO.sub.4).
摘要翻译： 公开了一种新型的水性电解活化溶液和电镀锆锆合金的方法。 新型含水电解活化溶液由约10至约20克/升氟化氢铵（NH 4 FHF）和约0.75至2克/升硫酸（H 2 SO 4）组成。
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公开(公告)号：US4992232A
公开(公告)日：1991-02-12
申请号：US380790
申请日：1989-07-17
申请人： Robert L. Cowan, II , Dragomir Duitna , Robert J. Law , Chien-Chang Lin , Carl P. Ruiz , James L. Simpson
发明人： Robert L. Cowan, II , Dragomir Duitna , Robert J. Law , Chien-Chang Lin , Carl P. Ruiz , James L. Simpson
IPC分类号： G21C1/00 , G21C19/307
CPC分类号： G21C19/307
摘要： In a boiling water reactor nuclear plant, hydrogen is injected into the feed water to neutralize radiolysis which causes stress corrosion in stainless steel components. It has been discovered that by inhibiting volatile ammonia, and other gaseous nitrogen compounds from leaving the liquid phase portions of the plant to the steam phase portions of the plant, radiation is reduced to acceptable levels. Formation of ammonia is inhibited chemically, by altering the reaction paths for volatile nitrogen species with trace additives in the parts per billion range, suitable additives include nitrous oxide, copper, zinc, carbon dioxide, and other components. It has also been found that by manipulating the pH, the formation of the voltage nitrogen compounds, especially ammonia, is decreased. Similarly, by physically altering plant operating conditions to reduce sparging or scrubbing of the gases from areas of high radiation, confinement of the N-16 within the liquid phase of the plant within the reactor vessel occurs. It is further found that by decreasing the total hydrogen concentration in the core region, the N-16 volatility can be limited. This includes alternate hydrogen injection points and enhancement of the hydrogen-oxygen recombination reaction by e.g., catalysis by radiation or by surfaces. The possibility of increasing the N-16 holdup time in the steam phase is also considered. Finally, the concept of operating at a higher electrochemical potential which requires a lower hydrogen concentration and hence less N-16 converted to the volatile form is also described.
摘要翻译： 在沸水反应堆核电站中，将氢气注入给水中以中和放射分解，这导致不锈钢部件产生应力腐蚀。 已经发现，通过抑制挥发性氨和其它气态氮化合物将植物的液相部分离开到植物的蒸汽相部分，辐射降低到可接受的水平。 通过用十分之一范围的微量添加剂改变挥发性氮物种的反应路径，化学物质的形成被抑制，合适的添加剂包括一氧化二氮，铜，锌，二氧化碳等组分。 还已经发现，通过操纵pH，电压氮化合物，特别是氨的形成减少。 类似地，通过物理地改变植物操作条件以减少来自高辐射区域的气体的喷射或洗涤，发生在反应器容器内的植物的液相内的N-16的限制。 进一步发现，通过降低核心区域中的总氢浓度，可以限制N-16挥发性。 这包括交替的氢注入点和通过例如通过辐射或通过表面的催化来增强氢 - 氧复合反应。 也考虑在蒸汽阶段增加N-16滞留时间的可能性。 最后，还描述了在更高的电化学电势下操作的概念，其需要较低的氢浓度并因此减少转化为挥发性形式的N-16。
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