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Melt-dilute spent nuclear fuel form - fabrication and metallurgical characteristics

Technical Report ·
DOI:https://doi.org/10.2172/1734667· OSTI ID:1734667
 [1];  [1];  [1]
  1. Savannah River Nuclear Solutions (SRNS), Aiken, SC (United States); Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)
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The melt-dilute treatment technology developed at SRS consolidates fuel assemblies by a melting/casting process in which depleted uranium is added to reduce enrichment below 20% 235U. Preliminary criticality analyses have shown that minor amounts of neutron-absorbing materials are needed to demonstrate criticality control (i.e., maintain keff < 0.95) for melt-dilute spent nuclear fuel (MD-SNF) form with 20% 235U enrichment. Therefore, it is necessary to demonstrate process and performance compatibility of neutron absorbing materials in the MD-SNF form. This report addresses the process compatibility of neutron absorbing materials for the uranium-aluminum alloy fuels. Studies on the process compatibility of neutron absorbing materials for the silicide and oxide fuels and the performance compatibility of the resulting SNF form is in progress under the melt-dilute qualification program. The SNF form compatibility studies will provide data on the effect of neutron absorbing material additions on MD-SNF corrosion and corrosion products, microstructure, and homogeneity to support performance assessment and criticality analyses under repository relevant environments. Results of this ongoing work will be included in the final report of the melt-dilute SNF form characteristics.
Research Organization:
Savannah River Site (SRS), Aiken, SC (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC09-08SR22470; AC09-96SR18500
OSTI ID:
1734667
Report Number(s):
WSRC-TR--2000-00349
Country of Publication:
United States
Language:
English

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Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS