Open AccessEstimation of the development possibility of the ABC/ATW fuel cycle based on LiF-BeF{sub 2} fuel salt. Part 2
Author(s) -
A. V. Bychkov,
V. S. Naumov
Publication year - 1994
Language(s) - English
Resource type - Reports
DOI - 10.2172/72962
Subject(s) - actinide , nuclear fission product , fission products , salt (chemistry) , molten salt reactor , molten salt , solubility , chemistry , spent nuclear fuel , nuclear fuel , fluoride , fuel cycle , radiochemistry , fission , nuclear chemistry , inorganic chemistry , waste management , organic chemistry , engineering , nuclear physics , neutron , physics
The aim of the first chapter was generalization of data on solubility and equilibrium states of fission product and actinide fluorides in fluoride salt melts-solvents and fuel composition melts based on LiF-BeF{sub 2} mixture which was proposed as fuel basis for ABC/ATW facility. The second chapter is devoted to description of processes proposed for the chemical-technological complex of the ABC/ATW facility and their physico-chemical peculiarities. The complex is responsible for the removal of fission products and actinides from irradiated fuel salt