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Determinations of plutonium and curium in the insoluble materials of spent fuel dissolver solutions at the Tokai Reprocessing Plant

机译:Toka再加工厂废燃料溶解溶液溶液不溶性材料中钚和含含量的测定

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Plutonium and curium in the insoluble materials of spent fuel dissolver solutions were determined by alpha spectrometry after sulfate fusion of insoluble materials and purification of plutonium and curium in the fused solution. A small amount of plutonium exists in insoluble materials such as sludge and chips of cladding tube, which are generated during dissolution of spent fuel and are removed from the dissolver solution by a pulse filter at clarification process. The filtered insoluble materials are removed by washing with water from the reverse direction and the washed filter is transferred to a waste storage area, but it is supposed that fine particles of the insoluble materials slightly remain in the pulse filter. For the measurement of plutonium in the spent pulse filter by non-destructive analysis, High Level Neutron Coincidence Counter (HLNCC) based on passive neutron measurement has been studied for safeguards under the cooperation between JAEA and the Los Alamos National Laboratory (LANL). In the HLNCC measurements, detections of neutron emission from the sample are dominated by curium-244. It is therefore difficult to detect the neutron emitted by plutonium. However, if the ratios of plutonium to curium-244 for insoluble materials in spent fuel dissolver solution were known, the amount of plutonium in the pulse filter can be calculated from a passive neutron measurement. The measurement data of plutonium and curium-244 in the insoluble materials of dissolver solution has not been reported in the case of engineering scale facilities. In this work, three kinds of insoluble materials were filtrated from spent PWR fuel dissolver solutions and were completely fused with ammonium hydrogen sulfate. Plutonium in the sample was selectively extracted with TEVA resin. Curium was also purified from plutonium and other fission products with di (2-ethylhexl) phosphoric acid (HDEHP). Each sample was electrodeposited onto stainless steel discs, and plutonium and curium were determined by alpha spectrometry, respectively. The amounts of plutonium and curium-244 in insoluble materials were in the range from 3.7 mg g-1 to 17 mg g-1 and in the range 0.058 g g-1 to 0.24 g g-1. They are valuable data for evaluation of the ratios of plutonium to curium-244.
机译:钚和乏燃料溶解溶液的不溶物锔通过不溶物的硫酸盐融合和钚和锔的纯化在稠合溶液后α光谱测定法确定。钚少量存在于不溶性物质如污泥和包层管的芯片,这是废燃料的溶解期间产生并从在澄清过程由脉冲滤波器溶解器溶液被去除。经过滤的不溶性物质通过用水洗涤除去来自反方向和洗过的过滤器转移至废弃物存储区,但假定不溶性物质的细颗粒略微保留在脉冲滤波器。对于钚的废脉冲过滤器通过非破坏性分析测量,基于无源中子测量高水平中子符合计数器(HLNCC)已经研究了JAEA和洛斯阿拉莫斯国家实验室(LANL)的合作下保障。在HLNCC测量,从样品发射中子的检测是通过锔-244为主。因此,难以为检测由钚发射的中子。然而,如果钚到锔-244的比例为不溶性物质在乏燃料溶解溶液是已知的,在脉冲滤波器钚的量可以从被动中子测量来计算。钚和锔-244的中的溶解溶液中的不溶性物质的测量数据还没有被报道的工程设施规模的情况下。在这项工作中三种不溶物质被从废PWR燃料溶解溶液过滤,并用硫酸氢铵完全熔合。样品中的钚选择性地用TEVA树脂萃取。锔也从钚等裂变产物与二(2- ethylhexl)磷酸(HDEHP)纯化。将每个样品电沉积到不锈钢盘,和钚和锔通过α光谱测定法,分别测定。在不溶性物质钚和锔-244的量为的范围为3.7毫克的G-1至17毫克的G-1,并在范围0.058克G-1至0.24克G-1。他们是钚的比率评价锔-244有价值的数据。

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