Open AccessAssessment of Pyrochemical Methods for the Molten Salt Reactor Fuel Clean-Up
Author(s) -
Sylvie Rouquette-Sanchez
Publication year - 2004
Publication title -
ecs proceedings volumes
Language(s) - English
Resource type - Journals
eISSN - 2576-1579
pISSN - 0161-6374
DOI - 10.1149/200424.0738pv
Subject(s) - molten salt reactor , molten salt , neptunium , fission products , actinide , spent nuclear fuel , thorium fuel cycle , uranium , liquid fluoride thorium reactor , chemistry , extraction (chemistry) , mox fuel , nuclear fuel , radiochemistry , nuclear fuel cycle , materials science , plutonium , nuclear chemistry , nuclear reactor core , inorganic chemistry , nuclear engineering , metallurgy , radioactive waste , chromatography , engineering
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