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1.发明授权Sintered nuclear fuel body and method for producing a sintered nuclear fuel body 失效烧结核燃料体及烧结核燃料体的制造方法
公开(公告)号：US5894501A
公开(公告)日：1999-04-13
申请号：US893820
申请日：1997-07-11
申请人： Wolfgang Doerr , Harald Cura , Gerhard Gradel
发明人： Wolfgang Doerr , Harald Cura , Gerhard Gradel
CPC分类号： G21C3/623 , Y02E30/38 , Y10S376/901
摘要： A sintered nuclear fuel body includes (U, Pu)O.sub.2 mixed crystals having a mean particle size in a range from 7.5 .mu.m to 50 .mu.m. This sintered nuclear fuel body has a high retention capacity for fission gas in a power reactor. In order to produce the sintered nuclear fuel body by sintering a body in a hydrogen-containing sintering atmosphere, a powered substance selected from the group consisting of aluminum oxide, titanium oxide, niobium oxide, chromium oxide, aluminum stearate, aluminum distearate and aluminum tristearate is added to the starting powder for the body. As an alternative or in addition, the body made from the starting powder is sintered during a holding period of 10 minutes to 8 hours at a sintering temperature of 1400.degree. C. to 1800.degree. C. in a hydrogen-containing sintering atmosphere, initially with an oxygen partial pressure of 10.sup.-10 to 10.sup.-20 bar and then from 10.sup.-8 to 10.sup.-10 and then cooled in a hydrogen-containing atmosphere having an oxygen partial pressure of 10.sup.-10 to 10.sup.-20 bar.
摘要翻译： 烧结核燃料体包括（U，Pu）O 2混合晶体，其平均粒度在7.5μm至50μm的范围内。 这种烧结核燃料体在动力反应堆中具有高裂变气体的保留能力。 为了通过在含氢烧结气氛中烧结体来生产烧结核燃料体，选自氧化铝，氧化钛，氧化铌，氧化铬，硬脂酸铝，二硬脂酸铝和三硬脂酸铝的动力物质 加入到身体的起始粉末中。 作为替代或另外，在含氢烧结气氛中，在1400℃至1800℃的烧结温度下，在起始粉末制成的本体在10分钟至8小时的保持期间内烧结，最初与 氧分压为10-10至10-20巴，然后为10-8至10-10，然后在氧分压为10-10至10-20巴的含氢气氛中冷却。
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公开(公告)号：US4671904A
公开(公告)日：1987-06-09
申请号：US701566
申请日：1985-02-14
申请人： Wolfgang Dorr , Gerhard Gradel , Martin Peehs
发明人： Wolfgang Dorr , Gerhard Gradel , Martin Peehs
摘要： UO.sub.2 base powder exhibiting any specific surface and crystallite diameter properties is mixed with rare earth (SE) oxide-containing powder, the particles of which exhibit at least in one surface layer, a crystal lattice of the fluorite type, with the stoichiometric composition (SE.sub.0.5, U.sub.0.5) 0.sub.2.00 and/or form it in sintering; and is compacted to form compacts which are sintered in a gas atmosphere with reducing action at 1500.degree. C. to 1750.degree. C. to form high-density sintered bodies.
摘要翻译： 表现出任何比表面和微晶直径性质的UO2基粉末与含稀土（SE）氧化物的粉末混合，其中颗粒至少在一个表面层中呈现萤石型晶格，具有化学计量组成（SE0 .5，U0.5）02.00和/或在烧结中形成; 并压实成型，在1500〜1750℃的还原作用的气体气氛中烧结，形成高密度烧结体。
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公开(公告)号：US4438050A
公开(公告)日：1984-03-20
申请号：US190981
申请日：1980-09-26
申请人： Wolfgang Dorr , Gerhard Gradel , Martin Peehs
发明人： Wolfgang Dorr , Gerhard Gradel , Martin Peehs
摘要： Manufacture of very dense oxidic fuel bodies of UO.sub.2 with rare earth oxides in which pressed blanks are subjected to sintering in an oxidizing atmosphere at relatively low temperature and are sintered in a reducing atmosphere at a higher temperature. This avoids sintering-inhibiting phases and permits very dense bodies with greater content of rare earth oxides to be produced.
摘要翻译： 用稀土氧化物制造非常致密的氧化物燃料体，其中压坯在氧化性气氛中在较低温度下进行烧结，并在较高温度下还原气氛中烧结。 这避免了烧结抑制阶段，并且允许产生具有更多含量的稀土氧化物的非常致密的体。
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公开(公告)号：US06617558B2
公开(公告)日：2003-09-09
申请号：US10180441
申请日：2002-06-26
IPC分类号： H05B680
CPC分类号： H05B6/6402 , F27B21/00 , G21C3/623 , H05B6/705 , H05B6/708 , H05B6/80 , H05B2206/046 , Y02E30/38
摘要： A furnace is provided for microwave sintering of nuclear fuel. A stationary wave is generated in an antenna cavity and used to extract microwaves through slots into a resonance chamber containing the nuclear fuel. A position of the slots is adjusted in such a way that a predetermined temperature profile is produced in the nuclear fuel.
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公开(公告)号：US06437303B1
公开(公告)日：2002-08-20
申请号：US09643183
申请日：2000-08-21
IPC分类号： H05B664
CPC分类号： H05B6/6402 , F27B21/00 , G21C3/623 , H05B6/705 , H05B6/708 , H05B6/80 , H05B2206/046 , Y02E30/38
摘要： A method and a furnace are provided for microwave sintering of nuclear fuel. A stationary wave is generated in an antenna cavity and used to extract microwaves through slots into a resonance chamber containing the nuclear fuel. A position of the slots is adjusted in such a way that a predetermined temperature profile is produced in the nuclear fuel.
摘要翻译： 提供了一种用于微波烧结核燃料的方法和炉。 在天线腔中产生静止波，用于通过狭缝将微波提取到包含核燃料的共振室中。 调节槽的位置，使得在核燃料中产生预定的温度曲线。
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公开(公告)号：US06235223B1
公开(公告)日：2001-05-22
申请号：US09185841
申请日：1998-11-04
申请人： Wolfgang Doerr , Harald Cura , Gerhard Gradel
发明人： Wolfgang Doerr , Harald Cura , Gerhard Gradel
IPC分类号： G21C2100
CPC分类号： G21C3/623 , Y02E30/38 , Y10S376/901
摘要： A sintered nuclear fuel body includes (U, Pu)O2 mixed crystals having a mean particle size in a range from 7.5 &mgr;m to 50 &mgr;m. This sintered nuclear fuel body has a high retention capacity for fission gas in a power reactor. In order to produce the sintered nuclear fuel body by sintering a body in a hydrogen-containing sintering atmosphere, a powered substance selected from the group consisting of aluminum oxide, titanium oxide, niobium oxide, chromium oxide, aluminum stearate, aluminum distearate and aluminum tristearate is added to the starting powder for the body. As an alternative or in addition, the body made from the starting powder is sintered during a holding period of 10 minutes to 8 hours at a sintering temperature of 1400° C. to 1800° C. in a hydrogen-containing sintering atmosphere, initially with an oxygen partial pressure of 10−10 to 10−20 bar and then from 10−8 to 10−10 and then cooled in a hydrogen-containing atmosphere having an oxygen partial pressure of 10−10 to 10−20 bar.
摘要翻译： 烧结核燃料体包括（U，Pu）O 2混合晶体，其平均粒度在7.5μm至50μm的范围内。 这种烧结核燃料体在动力反应堆中具有高裂变气体的保留能力。 为了通过在含氢烧结气氛中烧结体来生产烧结核燃料体，选自氧化铝，氧化钛，氧化铌，氧化铬，硬脂酸铝，二硬脂酸铝和三硬脂酸铝的动力物质 加入到身体的起始粉末中。 作为替代或另外，在含氢烧结气氛中，在1400℃至1800℃的烧结温度下，在10分钟至8小时的保持时间内，由起始粉末制成的体系烧结，最初与 氧分压为10-10至10-20巴，然后为10-8至10-10，然后在氧分压为10-10至10-20巴的含氢气氛中冷却。
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公开(公告)号：US4512939A
公开(公告)日：1985-04-23
申请号：US431615
申请日：1982-09-30
摘要： Method for the manufacture of oxidic sintered nuclear fuel bodies by compacting UO.sub.2 -starting powder or a mixture of UO.sub.2 -and PuO.sub.2 starting powder which contains up to 10% by weight rare-earth oxide, especially Gd.sub.2 O.sub.3, as an additive into blanks and subsequent densification of these blanks by a heat treatment in a sintering atomsphere with reducing action. The UO.sub.2 -starting powder used for compacting has a specific surface in the range of 2 to 4.5 m.sup.2 /g and/or a mean crystallite diameter in the range of 80 nm to 250 nm, and the heat treatment in the sintering atmosphere with reducing action is carried out at a temperature in the range of 1,500.degree. C. to 1,750.degree. C.
摘要翻译： 用于通过压制含氧化物起始粉末或含有高达10重量％稀土氧化物，特别是Gd 2 O 3的UO 2和PuO 2起始粉末的混合物作为添加剂进入坯料并随后的致密化来制造氧化烧结核燃料体的方法 这些坯料通过在具有还原作用的烧结原子团中进行热处理。 用于压实的UO2起始粉末的比表面积在2〜4.5m 2 / g的范围内和/或在80nm〜250nm的范围内的平均微晶直径，并且具有还原作用的烧结气氛中的热处理 在1500〜1750℃的温度下进行。
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公开(公告)号：US06808656B2
公开(公告)日：2004-10-26
申请号：US10108115
申请日：2002-03-27
申请人： Gerhard Gradel , Wolfgang Dörr
发明人： Gerhard Gradel , Wolfgang Dörr
IPC分类号： G21C2100
CPC分类号： G21C3/623 , G21C21/02 , G21Y2002/104 , G21Y2002/207 , G21Y2002/304 , G21Y2004/10 , G21Y2004/20 , Y02E30/38
摘要： A nuclear fuel sintered body is produced from a powder which contains at least one fissile heavy metal oxide. During the further treatment of the powder over the course of the process preceding the sintering operation, a dopant that contains at least 100 ppm of an iron oxide compound is added to the powder. The powder is a UO2-containing powder obtained from a dry-chemical conversion process, and if appropriate, a powder which contains further fissile heavy metal oxide (U3O8, PuO2, inter alia). As a result, the sintered body is provided with high plasticity combined, at the same time, with a large grain size. This advantageously reduces an interaction between the nuclear fuel sintered body and a fuel rod cladding tube during an operation of the reactor.
摘要翻译： 核燃料烧结体由含有至少一种裂变重金属氧化物的粉末制成。 在烧结操作之前的过程中粉末的进一步处理期间，向粉末中加入含有至少100ppm氧化铁化合物的掺杂剂。 该粉末是由干化学转化法得到的含有氧化铝的粉末，如果合适的话，还含有其它易裂变重金属氧化物（U3O8，PuO2等）的粉末。 结果，烧结体具有高可塑性，同时具有大的晶粒尺寸。 这有利地降低了反应器操作期间核燃料烧结体和燃料棒包层管之间的相互作用。
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公开(公告)号：US5642390A
公开(公告)日：1997-06-24
申请号：US599386
申请日：1996-02-09
申请人： Harald Cura , Martin Peehs , Gerhard Gradel , Alfons Roppelt , Erhard Ortlieb , Richard A. Perkins
发明人： Harald Cura , Martin Peehs , Gerhard Gradel , Alfons Roppelt , Erhard Ortlieb , Richard A. Perkins
摘要： A uranium-containing nuclear-fuel sintered pellet containing UO.sub.2, (U, Pu)O.sub.2, (U, Th)O.sub.2, (U, RE)O.sub.2, (U, Pu, Th)O.sub.2, (U, Pu, RE)O.sub.2, (U, Th, RE)O.sub.2 or (U, Pu, Th, RE)O.sub.2, wherein RE=rare earth, has a sintered-pellet surface layer being formed of at least 80% by volume of a chemical boron compound UB.sub.x or (U, . . . )B.sub.x, wherein x=2;4;6 or 12, and a remainder of the sintered pellet containing at most 5% by volume of the chemical boron compound. A nuclear-reactor fuel assembly has a fuel rod containing such a uranium-containing nuclear-fuel sintered pellet in a cladding tube with the boron as a burnable absorber for thermal neutrons. The surface layer having the chemical boron compound is obtained by treating the nuclear-fuel sintered pellet with boron or a boron-containing chemical compound at an appropriately high treatment temperature.
摘要翻译： 含有UO2，（U，Pu）O2，（U，Th）O2，（U，RE）O2，（U，Pu，Th）O2，（U，Pu，RE）O2的含铀核燃料烧结颗粒 ，（U，Th，RE）O 2或（U，Pu，Th，RE）O 2，其中RE =稀土，具有烧结颗粒表面层，其由至少80体积％的化学硼化合物UBx或 （U，...）Bx，其中x = 2; 4; 6或12，剩余的烧结颗粒含有至多5体积％的化学硼化合物。 核反应堆燃料组件具有在包覆管中含有这种含铀的核燃料烧结颗粒的燃料棒，其中硼作为热中子的可燃性吸收剂。 具有化学硼化合物的表面层通过在适当高的处理温度下用硼或含硼化合物处理核燃料烧结颗粒而获得。
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公开(公告)号：US4663112A
公开(公告)日：1987-05-05
申请号：US589513
申请日：1984-03-14
申请人： Gerhard Gradel , Peter Wahode , Wolfgang Dorr
发明人： Gerhard Gradel , Peter Wahode , Wolfgang Dorr
摘要： Method for determining the contents of a fuel rod within a testing range extending in the longitudinal direction of the fuel rod, characterized by the features that(a) the position of a test coil concentrically surrounding the fuel rod is changed from the beginning to the end of the testing range, and(b) in the process, the impedance of the test coil is measured as a function of its position,(c) the test coil is fed with an a-c voltage,(d) the frequency of which is so low that the measurement value in the region of a fuel pellet of pure uranium dioxide is clearly distinguished from that which is measured in the region of a doped fuel pellet.
摘要翻译： 在燃料棒的纵向延伸的测试范围内确定燃料棒的内容物的方法，其特征在于，（a）同心地围绕燃料棒的测试线圈的位置从开始到结束 （b）在该过程中，测试线圈的阻抗作为其位置的函数被测量，（c）测试线圈被馈送交流电压，（d）其频率是如此 低纯度二氧化铀的燃料颗粒区域中的测量值与在掺杂燃料颗粒的区域中测量值的清楚区别。
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