Radiation measurements of uranium ingots from the electrometallurgical treatment of spent fuel.

Westphal, B. R. ; Liaw, J. R. ; Krsul, J. R. ; Maddison, D. W. ; Jensen, B. A.

Argonne National Laboratory

关键词: Uranium;    Gamma Spectroscopy;    Shielding;    Processing;    Optimization;   

DOI  :  10.2172/820528
RP-ID  :  ANL-NT-188
RP-ID  :  W-31-109-ENG-38
RP-ID  :  820528

美国|英语

来源: UNT Digital Library

【 摘 要 】

Radiation measurements and gamma spectroscopy analyses were made on numerous uranium ingots produced during the treatment of Experimental Breeder Reactor-II (EBR-II) spent nuclear fuel. The objective of these measurements was to provide background data for shielding concerns and potential process optimization. The uranium ingots resulted from the processing of both driver and blanket fuel by the electrometallurgical treatment process. The observed variation in the measurements was traced to the levels of certain fission product residues that remained in the uranium ingots produced during spent fuel treatment. A minor process change to hold the material at an elevated temperature for a specified length of time was found to significantly reduce concentrations of high-activity fission products and, thus the radiation field.