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公开(公告)号：US4816193A
公开(公告)日：1989-03-28
申请号：US99687
申请日：1987-09-18
申请人： Martin Peehs , Heinrich Bayer , Ulrich Jenczio , Jurgen Laucht , Sieghard Hellmann , Gerhard Dichtjar , Wolfgang Dorr , Georg Maier
发明人： Martin Peehs , Heinrich Bayer , Ulrich Jenczio , Jurgen Laucht , Sieghard Hellmann , Gerhard Dichtjar , Wolfgang Dorr , Georg Maier
摘要： Method for manufacturing sintered oxidic nuclear fuel bodies by molding uranium oxide starting powder, a mixture of uranium oxide and plutonium oxide starting powder or of uranium-plutonium oxide mixed-crystal starting powder to form blanks and by a heat treatment of these blanks with a U.sub.4 O.sub.9 or (U, Pu).sub.4 O.sub.9 crystal phase developed in them to a degree which can be crystallographically detected at a sintering temperature in the range of 1000.degree. to 1400.degree. C. in an oxidizing and subsequently in a reducing gas atmosphere. The starting powder and/or the blanks are preroasted at a roasting temperature below the sintering temperature in a roasting gas atmosphere with oxidizing action and with an oxygen potential in which the U.sub.4 O.sub.9 (U, Pu).sub.4 O.sub.9 crystal phase is developed and cooled down subsequently to a starting temperature below the roasting temperature in an inert or oxidizing cooling-down gas atmosphere. Starting from this starting temperature, the blanks are heated to the sintering temperature in an inert or oxidizing heating gas atmosphere while maintaining the U.sub.4 O.sub.9 or the (U, Pu).sub.4 O.sub.9 crystal phase.
摘要翻译： 通过模制氧化铀原料粉末，氧化铀和钚氧化物起始粉末或铀 - 钚氧化物混合起始粉末的混合物来形成烧结氧化物核燃料体的方法以形成坯料并且通过用U4O9热处理这些坯料 或（U，Pu）4 O 9结晶相在一定程度上可以在氧化并随后在还原气体气氛中在1000-1400℃范围内的烧结温度下进行晶体学检测。 起始粉末和/或坯料在具有氧化作用的焙烧气体气氛中的焙烧温度下焙烧，并且其中U4O9（U，Pu）4 O9晶相的氧电位被开发并随后冷却 在惰性或氧化冷却气氛中的起始温度低于焙烧温度。 从该起始温度开始，将坯料在惰性或氧化加热气体气氛中加热至烧结温度，同时保持U4O9或（U，Pu）4 O9晶相。
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公开(公告)号：US4578229A
公开(公告)日：1986-03-25
申请号：US436303
申请日：1982-10-25
申请人： Helmut Assmann , Gerhard Dichtjar , Wolfgang Dorr , Georg Maier , Viktor Mathieu , Martin Peehs
发明人： Helmut Assmann , Gerhard Dichtjar , Wolfgang Dorr , Georg Maier , Viktor Mathieu , Martin Peehs
摘要： Method for the manufacture of oxidic nuclear fuel bodies by a heat treatment of blanks obtained from UO.sub.2 starting power or a mixture of UO.sub.2 and PuO.sub.2 starting powder at a treatment temperature in the range of 1000.degree. C. to 1400.degree. initially in a gas atmosphere with oxidizing action and subsequently in a gas atmosphere with reducing action. The oxygen potential of the gas atmosphere with oxidizing action is kept in a range in which a crystallographically demonstrable U.sub.4 O.sub.9 or (U, Pu).sub.4 O.sub.9 crystal phase is generated in the blanks during the heating to the treatment temperature in this gas atmosphere with oxidizing action.
摘要翻译： 在氧气核燃料体的热处理中，由UO2起动力获得的坯料或者在1000℃至1400℃的处理温度下的UO2和PuO2起始粉末的混合物在气体气氛中进行热处理的方法， 氧化作用，随后在具有还原作用的气体气氛中。 具有氧化作用的气体气氛的氧气被保持在在氧化作用的气体气氛中加热至处理温度期间在坯料中产生结晶学上可见的U4O9或（U，Pu）4O9结晶相的范围内。
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公开(公告)号：US4655978A
公开(公告)日：1987-04-07
申请号：US592869
申请日：1984-03-23
申请人： Helmut Assmann , Wolfgang Dorr , Georg Maier , Martin Peehs
发明人： Helmut Assmann , Wolfgang Dorr , Georg Maier , Martin Peehs
IPC分类号： C04B35/64 , C04B35/51 , F27B9/02 , F27B9/04 , F27B9/08 , F27B9/22 , G21C3/62 , G21C21/02 , G21C21/00 , F27B14/00 , F27D19/00
摘要： Method for sintering blanks into fuel pellets, in which the blanks are moved through the muffle of a tunnel furnace by pushing the blanks through the muffle on a guiding device which goes through the muffle and protrudes therefrom at least on the input side, in the form of a single-layer column of abutting blanks.
摘要翻译： 将坯料烧结成燃料颗粒的方法，其中通过将坯料通过马弗管推动穿过马弗管并且至少在输入侧从其引出的引导装置将坯料移动通过隧道炉的马弗管，其形式 的单层柱的邻接坯料。
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公开(公告)号：US4795341A
公开(公告)日：1989-01-03
申请号：US3574
申请日：1987-01-15
申请人： Helmut Assmann , Wolfgang Dorr , Georg Maier , Martin Peehs
发明人： Helmut Assmann , Wolfgang Dorr , Georg Maier , Martin Peehs
IPC分类号： C04B35/64 , C04B35/51 , F27B9/02 , F27B9/04 , F27B9/08 , F27B9/22 , G21C3/62 , G21C21/02 , F27D3/04
摘要： Method for sintering blanks into fuel pellets, in which the blanks are moved through the muffle of a tunnel furnace by pushing the blanks through the muffle on a guiding device which goes through the muffle and protrudes therefrom at least on the input side, in the form of a single-layer column of abutting blanks.
摘要翻译： 将坯料烧结成燃料颗粒的方法，其中通过将坯料通过马弗管推动穿过马弗管并且至少在输入侧从其引出的引导装置将坯料移动通过隧道炉的马弗管，其形式 的单层柱的邻接坯料。
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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：US4774051A
公开(公告)日：1988-09-27
申请号：US24819
申请日：1987-03-12
申请人： Martin Peehs , Wolfgang Dorr
发明人： Martin Peehs , Wolfgang Dorr
CPC分类号： G21C3/18 , G21C3/623 , G21Y2002/201 , G21Y2004/10 , G21Y2004/40 , Y02E30/38
摘要： A sintered nuclear fuel compact of UO.sub.2 or the mixed oxides (U, Pu)O.sub.2 and (U, Th)O.sub.2, with which reactivity losses in a nuclear reactor having relatively long fuel element cycles are avoided, has in its sintered matrix neutron poison in the chemical compound form UB.sub.x with x=2; 4 and/or 12 and/or B.sub.4 C. A sintered nuclear fuel compact of this kind is produced by sintering from a compact comprising a mixture of at least one of the mixture components UO.sub.2, PuO.sub.2, (U, Pu)O.sub.2 and (U, Th)O.sub.2 powder with UB.sub.x powder, where x=2; 4 and/or 12 and/or B.sub.4 C powder.
摘要翻译： UIO的烧结核燃料压块或避免在具有较长的燃料元件循环的核反应堆中的反应性损失的混合氧化物（U，Pu）O 2和（U，Th）O 2）在其烧结基质中子毒 化合物形式为UBx，x = 2; 4和/或12和/或B4C。 这种烧结核燃料压块是通过将包含至少一种混合物组分UO2，PuO2，（U，Pu）O2和（U，Th）O 2）粉末与UBx粉末的混合物的烧结制成的，其中x = 2; 4和/或12和/或B4C粉末。
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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：US4259155A
公开(公告)日：1981-03-31
申请号：US573072
申请日：1975-04-30
申请人： Martin Peehs , Manfred Hunner
发明人： Martin Peehs , Manfred Hunner
摘要： Fuel assemblies forming cores of gas-cooled reactors, operate at temperatures too high to permit the use of resilient contact elements for holding the fuel rods centered in the openings of the spacer grids of the fuel assemblies, solid and rigid contact elements not relying on resilience, being required. In such cases intercontacting surfaces of the fuel rod metal claddings and the spacer grid contact elements, are capable of sticking together, preventing relative sliding by these surfaces to accommodate thermally induced movements, resulting in the claddings being highly stressed. To prevent this, one or both of the intercontacting surfaces are roughened or otherwise processed to have peaks and valleys or depressions so that abrasion products are carried off between the peaks, permitting the intercontacting surfaces to remain relatively slidable with the result that the previously referred to stressing of the claddings is substantially reduced as compared to that resulting when there is surface sticking together.
摘要翻译： 形成气冷反应堆核心的燃料组件在太高的温度下工作，不能使用弹性接触元件将燃料棒保持在燃料组件间隔栅格的开口中心，而不依赖于弹性的固体和刚性接触元件 ，被要求。 在这种情况下，燃料棒金属包层和间隔栅格接触元件的接触表面能够粘合在一起，防止这些表面的相对滑动以适应热引起的运动，导致包层受到高应力。 为了防止这种情况，一个或两个接触表面被粗糙化或以其他方式处理以具有峰谷和凹陷，使得磨损产物在峰之间被移走，允许中间接触表面保持相对滑动，结果是先前提及 与表面粘合在一起时所产生的包层的应力显着降低。
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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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