Dose Contribution from High Level Waste Uranium and Plutonium. Revision 1
Radiological source terms for safety analyses traditionally have been curie lists of radionuclides. Converting the source term to dose values allows each radionuclide to be evaluated for its impact on dose, which is the purpose of the source term. This report is one in a series of reports establishing source terms for High Level Waste (HLW) by evaluating the dose impact of each radionuclide. These reports will be used in establishing the source terms to be used in HLW Safety Analysis Reports. The purpose of this report is to document the bounding element dose impact of uranium and plutonium in HLW. This technique (use of dose rather than curies) demonstrates vividly the relative importance of these nuclides in accident analyses. A large amount of available data permitted dose values to be established for uranium and plutonium; therefore, these two elements were evaluated independent of other nuclides. Solubility and adsorption data, available for these elements, allow bounding conditions to be established for their contribution to dose for various HLW processes.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 10124438
- Report Number(s):
- WSRC-TR--93-604-Rev.1; ON: DE95060093
- Country of Publication:
- United States
- Language:
- English
Similar Records
Supernate source term analysis: Revision 1
Sludge source term (PUREX process radionuclide dose impact)
Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel
Technical Report
·
Thu Oct 13 00:00:00 EDT 1994
·
OSTI ID:10105057
Sludge source term (PUREX process radionuclide dose impact)
Technical Report
·
Tue Jun 28 00:00:00 EDT 1994
·
OSTI ID:10104280
Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel
Technical Report
·
Sat Dec 31 23:00:00 EST 1994
·
OSTI ID:885845