Pablo Vacas-Arquero , Iván Sánchez-García , Hitos Galán
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引用次数: 0
Abstract
N,N,N′,N′-tetraoctyldiglycolamide (TODGA) is considered one of the most promising extractants for achieving the actinides recovery in the advanced nuclear fuel cycles due to its good extraction properties and resistance to degradation against the harsh process conditions, i.e. a high radiation field and high nitric acid concentrations where the spent nuclear fuel is dissolved. While its stability has been very well studied and its degradation products characterized, their impact on separating americium (Am) and curium (Cm) hasn't been fully investigated. This study presents from fundamental investigations to more realistic scenarios on how the accumulation of the degradation compounds of TODGA could affect the Am and Cm separation under Americium Selective (AmSel) process conditions. This study also considers some possibility of solving the problems caused by the accumulation of those compounds by adjusting different parameters in the stripping step of the AmSel process such as the concentration of SO3-Ph-BTBP or HNO3 in the aqueous phase.
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
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2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
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