Addendum to the Calcined Waste Storage at the Idaho Nuclear Technology Center

Staiger, M. D. ; Swenson, Michael ; Thomas, T. R.

Idaho Completion Project (ICP)

关键词: Waste Acceptance Criteria;    Reprocessing;    Radionuclides;    Liquid Wastes;    Chemicals;   

DOI  :  10.2172/910644
RP-ID  :  ICP/EXT-04-00370
RP-ID  :  DE-AC07-99ID-13727
RP-ID  :  910644

美国|英语

来源: UNT Digital Library

【 摘 要 】

This report is an addendum to the report Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center, INEEL/EXT-98-00455 Rev. 1, June 2003. The original report provided a summary description of the Calcined Solids Storage Facilities (CSSFs). It also contained dozens of pages of detailed data tables documenting the volume and composition (chemical content and radionuclide activity) of the calcine stored in the CSSFs and the liquid waste from which the calcine was derived. This addendum report compiles the calcine composition data from the original report. It presents the compiled data in a graphical format with units (weight percent, curies per cubic meter, and nanocuries per gram) that are commonly used in regulatory and waste acceptance criteria documents. The compiled data are easier to use and understand when comparing the composition of the calcine with potential regulatory or waste acceptance criteria. This addendum report also provides detailed explanations for the large variability in the calcine composition among the CSSFs. The calcine composition varies as a result of reprocessing different types of fuel that had different cladding materials. Different chemicals were used to dissolve the various types of fuel, extract the uranium, and calcine the resulting waste. This resulted in calcine with variable compositions. This addendum report also identifies a few trace chemicals and radionuclides for which the accuracy of the amounts estimated to be in the calcine could be improved by making adjustments to the assumptions and methods used in making the estimates.