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公开(公告)号：EP0098696A1
公开(公告)日：1984-01-18
申请号：EP83303397.0
申请日：1983-06-13
CPC分类号： G21C3/26 , G21C3/16 , G21Y2002/201 , G21Y2002/303 , G21Y2004/10 , G21Y2004/30 , Y02E30/40
摘要： A cylindrical fuel element having a sheath (11) contains a central core (12) of particulate depleted urania or other particulate fuel(s) of low enrichment. The central core is surrounded by an outer annular volume (13) of one or more particulate highly enriched fuels, thus providing a radial enrichment gradient ecross the fuel cross-section. The higher enriched particulate fuel is concentrated close to the sheath (11) and more nuclear events will take place near the sheath surface. The thermal efficacy of the fuel element is increased due to the shortened thermal conductance pathways through the poorly conductive urania. The fuel element's operating fue! centerline temperature at a given power output is significantly reduced. Preferably the particulate fuels are mixtures of three types of substantially spherical particles of different diameter sizes.
摘要翻译： 具有护套（11）的圆柱形燃料元件包含颗粒状贫化的尿素或其他富集浓度较低的颗粒燃料的中心核心（12）。 中心芯由一个或多个高度富集的高效燃料的外部环形容积（13）包围，从而提供了跨越燃料横截面的径向富集梯度。 较高浓缩的颗粒燃料集中在护套（11）附近，并且在护套表面附近将发生更多的核事件。 燃料元件的热效能由于导电性较差的尿素传导通路的缩短而增加。 燃油元件在给定功率输出下的燃油中心线工作温度显着降低。 优选地，颗粒燃料是不同直径尺寸的三种类型的基本上为球形的颗粒的混合物。
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2.发明公开Dissolution of Pu02 or Np02 using electrolytically regenerated reagents 失效Auflösungvon PuO2 oder NpO2 unter Anwendung von elektrolytisch regenerierten Reagenzien。
公开(公告)号：EP0089185A2
公开(公告)日：1983-09-21
申请号：EP83301319.6
申请日：1983-03-10
CPC分类号： C22B3/045 , G21C19/46 , Y02P10/234 , Y02W30/883
摘要： A process is disclosed for dissolving PuO 2 , or nuclear reactor fuel containing P U 0 2 and/or Np0 2 , in an aqueous medium containing nitric acid. The process comprises electrolytically continuously maintaining and regenerating an oxidizing reagent, being at least one compound of Ce, Ag, Co or Am which is soluble in the said medium. The regenerable reagent may be added to the mixture of oxide(s) and nitric acid, or may already be present in situ as a fission product or other nuclear reaction product in irradiated nuclear reactor fuel.
摘要翻译： 公开了用于将PuO 2或含有PuO 2和/或N p O 2的核反应堆燃料溶解在含有硝酸的水性介质中的方法。 所述方法包括连续维持和再生氧化试剂，所述氧化试剂是可溶于所述介质的Ce，Ag，Co或Am的至少一种化合物。 可再生试剂可以加入到氧化物和硝酸的混合物中，或者可以在辐照的核反应堆燃料中作为裂变产物或其他核反应产物原位存在。
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3.发明公开
公开(公告)号：EP0089185A3
公开(公告)日：1985-12-18
申请号：EP83301319
申请日：1983-03-10
CPC分类号： C22B3/045 , G21C19/46 , Y02P10/234 , Y02W30/883
摘要： A process is disclosed for dissolving PuO 2 , or nuclear reactor fuel containing P U 0 2 and/or Np0 2 , in an aqueous medium containing nitric acid. The process comprises electrolytically continuously maintaining and regenerating an oxidizing reagent, being at least one compound of Ce, Ag, Co or Am which is soluble in the said medium. The regenerable reagent may be added to the mixture of oxide(s) and nitric acid, or may already be present in situ as a fission product or other nuclear reaction product in irradiated nuclear reactor fuel.
摘要翻译： 公开了用于将PuO 2或含有PuO 2和/或N p O 2的核反应堆燃料溶解在含有硝酸的水性介质中的方法。 所述方法包括连续维持和再生氧化试剂，所述氧化试剂是可溶于所述介质的Ce，Ag，Co或Am的至少一种化合物。 可再生试剂可以加入到氧化物和硝酸的混合物中，或者可以在辐照的核反应堆燃料中作为裂变产物或其他核反应产物原位存在。
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公开(公告)号：EP0069520A2
公开(公告)日：1983-01-12
申请号：EP82303359.2
申请日：1982-06-28
发明人： Boldt, Allyn Lee
CPC分类号： B01D11/02 , B01D11/0223 , G21C19/38 , G21C19/44 , Y02W30/882 , Y10S422/903
摘要： An apparatus for continuously providing counter-current liquid-solid contact. A preferred embodiment of the apparatus includes an Archimedes' screw in the form of a spiral (24) and a distribution system which includes a central tube (6) disposed along the axis of the spiral. The central tube includes a plurality of weirs (20) and is in open communication with the spiral through a plurality of hollow spokes (22) fixed at one end to the spiral and at the other end to the central tube.
Dissolving solution is distributed by the distribution system to the spiral when it encounters nuclear material moving upward due to the pumping action of the spiral. The dissolved material moves counter-current to the nuclear material and is removed near the bottom of the apparatus.-
公开(公告)号：EP0178861A3
公开(公告)日：1987-06-03
申请号：EP85307291
申请日：1985-10-11
IPC分类号： G21C17/06
CPC分类号： G21C17/06
摘要： mechanism for testing fuel rods (34) in nuclear fuel bundles includes a carriage (16), carrying an elongated probe (21, and a grooved plate (26). The grooves (24) extend parallel to the probe (2) and are spaced by the same distances as rows of fuel rods (34) in the fuel bundle (36). They are connected at one end. A pin (22) on the carriage (16) fits in the grooves (24). A hydraulic cylinder (32) reciprocates the carriage (16) longitudinally of the grooves (24) and a pneumatic cylinder (38) urges it laterally, so that the pin (22) moves from one groove (24) to the next groove (24) at the end of each reciprocatory cycle.
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公开(公告)号：EP0081379A3
公开(公告)日：1984-11-07
申请号：EP82306518
申请日：1982-12-07
发明人： Gehri, Aime Albert
IPC分类号： G21C21/04
CPC分类号： G21C21/04
摘要： For the loading of spherical nuclear fuel in vertical fuel rods (2), a loading system includes a fuel rod support (4), a glovebox (22), a weighing station system in the gloveboxfor weighing a predetermined quantity of fuel spheres of each of a predetermined number of sphere sizes, a means (34) for feeding spherical fuel to the fuel rod (2), and transportation means (38) for moving the fuel between parts of the system.
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公开(公告)号：EP0178860A3
公开(公告)日：1987-05-27
申请号：EP85307290
申请日：1985-10-11
IPC分类号： G21C17/06
摘要： 57 Nuclear fuel rods (34) are checked for the presence of water in their interior by injecting bursts of ultrasound radially into the wall of each tube (34), producing echoing back and forth between the inner and outer surfaces of the tube (34). The rate of decay of this echoing indicates whether or not water is present.
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公开(公告)号：EP0069520B1
公开(公告)日：1986-08-06
申请号：EP82303359.2
申请日：1982-06-28
发明人： Boldt, Allyn Lee
CPC分类号： B01D11/02 , B01D11/0223 , G21C19/38 , G21C19/44 , Y02W30/882 , Y10S422/903
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公开(公告)号：EP0081378A3
公开(公告)日：1984-10-24
申请号：EP82306517
申请日：1982-12-07
发明人： Gehri, Aime Albert
IPC分类号： G21C21/04
CPC分类号： G21C21/04
摘要： A feeding apparatus for the loading of the spherical nuclear fuel into a fuel rod (2) feeds fuel of three differfent diameters into a fuel rod (2) so that the three different sized spheres are appropriately packed to achieve sufficient density of fuel to be used in a nuclear reactor. This is achieved by individually controlling the delivery flow rate of the nuclear fuel spheres of each size, using gates (114) defining an opening of a preselected width (w) and height (h).
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