Decontamination of Radionuclides From Concrete During and After Thermal Treatment

Spalding, Brian P. ; Bazant, Zdenek P. ; Murphy, Walter P.

Oak Ridge National Laboratory

关键词: Removal;    Heating;    Melting Points;    Decontamination;    Evaporation;   

DOI  :  10.2172/831201
RP-ID  :  EMSP-64896--2000
RP-ID  :  FG07-96ER45736
RP-ID  :  831201

美国|英语

来源: UNT Digital Library

【 摘 要 】

This project will determine the effect of heating concrete on its engineering properties and the potential to aid in removal of common DOE radionuclide contaminants including 137Cs, 90Sr, 60Co, and U. In the chemical properties subtask, effects on direct volatilization of radionuclides during heating, as well as their subsequent extractability behavior, will be established over a range of temperatures up to the melting point of Portland cement. The main objective of the mechanics and thermodynamics subtask of this investigation is to develop a powerful computational capability to evaluate the effects of various regimes of rapid heating of a contaminated concrete wall or slab.