Year
1980
Abstract
The overall objective of this paper is to evaluate the perfoimance of the CIVEX process, in terras of its diversion-proof characteristics and to assess the institutional problems of its deployment in the nuclear fuel cycle. A numerical scheme for stage calculations in a solvent extraction cascade, applicable to the Civex process, is formulated and the required experimentations and data for this scheme are specified. Also, an analytical approach to stage calculations, based on the theory of solvent extraction is developed and applied to the Civex flowsheet. It is shown that changing the flow rates in the extraction column of Civex can not lead to a decontaminated stream of Pu or U and Pu, but can lower the radiation levels so much that simple shielding procedures will reduce the health hazards to tolerable levels. The monitorinq and measurement techniques needed for Civex are analysed. It is concluded that from an analytical and accountability standpoint, operation of a Civex plant would demand extensive prior work on new measurement systems for process control and waste management. The institutional problems of deploying the Civex process are studied. It is shown that introduction of Civex to the nuclear fuel cycle has minor effects on proliferation and requires extensive international arrangements, however, it has positive effects on deterrence of proliferation by subnational groups.