Nuclear measurement in Pyro-processed wastes

Abstract

Nuclear fissile material was analyzed for the waste produced in the pyro-process. Nuclear waste is produced at each stage in the pyro-process, spent fuel head-end, major group recovery area and TRU-RE process. Each yields waste of different material composition and properties. Chemical analysis is basically determined for the measurement of nuclear material content. However, the possibility of non-destructive analysis techniques were examined as an additional and supplementary way for cost effectiveness and time saving in the nuclear material analysis. Examinations were undertaken on RE-salt waste, anode sludge, and hull. A gamma peak of Cm244 and Pu239 was simulated for the RE waste. The peak was well distinguishable in the waste. The linearity in the gamma measurement was approved with the content increase in the plutonium isotope. For fissile assay in anode sludge and hull, a neutron method was suggested. From the simulation results, a probable technique was recommended for plutonium content assay in each waste of the pyro-process. An accurate fissile assay will contribute to an increased safeguards for the pyro-processing system and international credibility for the reuse of fissile materials in the fuel cycle.