Premium
Process for fission‐product removal from uranium‐Bismuth reactor fuels by use of fused‐salt extraction
Author(s) -
Dwyer O. E.
Publication year - 1956
Publication title -
aiche journal
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.958
H-Index - 167
eISSN - 1547-5905
pISSN - 0001-1541
DOI - 10.1002/aic.690020207
Subject(s) - fission products , nuclear fission product , uranium , fuel element failure , extraction (chemistry) , molten salt , spent nuclear fuel , alkali metal , nuclear fuel cycle , nuclear fuel , actinide , bismuth , radiochemistry , waste management , thorium fuel cycle , fission , nuclear engineering , breeder (animal) , chemistry , enriched uranium , plutonium , materials science , neutron , nuclear chemistry , radioactive waste , mox fuel , nuclear physics , metallurgy , inorganic chemistry , engineering , chromatography , physics , organic chemistry , composite material , blanket
The liquid‐metal‐fuel reactor under development at the Brookhaven National Laboratory uses a fuel which is a solution of U 233 , Mg, and Zr in liquid bismuth. For a power breeder thermal reactor, high neutron economy is essential, and this calls for low concentrations of those fission products in the fuel which are high neutron capturers. Roughly 45% by weight of the fission products can be continuously removed from the fuel by salt extraction with alkali and alkaline‐earth fused‐salt mixtures. These fission products contain the highly “poisonous” rare earths. This paper will present a discussion of processdesign considerations and proposed flow sheets.