DSNF AND OTHER WASTE FORM DEGRADATION ABSTRACTION

CUNNANE, J.

United States. Department of Energy. Yucca Mountain Project Office.

关键词: Alloys;    Hydrides;    License Applications;    Oxides;    Waste Forms;   

DOI  :  10.2172/886565
RP-ID  :  ANL-WIS-MD-000004 REV 04
RP-ID  :  AC28-01RW12101
RP-ID  :  886565

美国|英语

来源: UNT Digital Library

【 摘 要 】

Several hundred distinct types of DOE-owned spent nuclear fuel (DSNF) may potentially be disposed in the Yucca Mountain repository. These fuel types represent many more types than can be viably individually examined for their effect on the Total System Performance Assessment for the License Application (TSPA-LA). Additionally, for most of these fuel types, there is no known direct experimental test data for the degradation and dissolution of the waste form in repository groundwaters. The approach used in the TSPA-LA model is, therefore, to assess available information on each of 11 groups of DSNF, and to identify a model that can be used in the TSPA-LA model without differentiating between individual codisposal waste packages containing different DSNF types. The purpose of this report is to examine the available data and information concerning the dissolution kinetics of DSNF matrices for the purpose of abstracting a degradation model suitable for use in describing degradation of the DSNF inventory in the Total System Performance Assessment for the License Application. The data and information and associated degradation models were examined for the following types of DSNF: Group 1--Naval spent nuclear fuel; Group 2--Plutonium/uranium alloy (Fermi 1 SNF); Group 3--Plutonium/uranium carbide (Fast Flux Test Facility-Test Fuel Assembly SNF); Group 4--Mixed oxide and plutonium oxide (Fast Flux Test Facility-Demonstration Fuel Assembly/Fast Flux Test Facility-Test Demonstration Fuel Assembly SNF); Group 5--Thorium/uranium carbide (Fort St. Vrain SNF); Group 6--Thorium/uranium oxide (Shippingport light water breeder reactor SNF); Group 7--Uranium metal (N Reactor SNF); Group 8--Uranium oxide (Three Mile Island-2 core debris); Group 9--Aluminum-based SNF (Foreign Research Reactor SNF); Group 10--Miscellaneous Fuel; and Group 11--Uranium-zirconium hydride (Training Research Isotopes-General Atomics SNF). The analyses contained in this document provide an ''upper-limit'' (i.e., instantaneous degradation) model for use in the TSPA-LA model. ''Best-estimate'' models for the degradation of the fuels in each of the DSNF groups are discussed to provide a basis for selecting the upper limit model for use in the TSPA-LA model. The instantaneous degradation model is chosen for use in the TSPA-LA model because the available information shows that the degradation rate of the N Reactor fuel (which constitutes most of the DSNF inventory) is very high and because the available qualified information is insufficient to justify use of a less conservative approach. The commercial spent nuclear fuel model will be used for naval spent nuclear fuel because it has been shown to be conservative for representing naval spent nuclear fuel.