SciTech Connect

Title: DISSOLUTION OF ZIRCALOY 2 CLAD UO2 COMMERCIAL REACTOR FUEL

DISSOLUTION OF ZIRCALOY 2 CLAD UO2 COMMERCIAL REACTOR FUEL The primary goal of this investigation was to evaluate the effectiveness of the chop-leach process, with nitric acid solvent, to produce a nominally 300 g/L [U] and 1 M [H{sup +}] product solution. The results of this study show that this processing technique is appropriate for applications in which a low free acid and moderately high U content are desired. The 7.75 L of product solution, which was over 450 g/L in U, was successfully diluted to produce about 13 L of solvent extraction feed that was 302 g/L in U with a [H{sup +}] in the range 0.8-1.2 M. A secondary goal was to test the effectiveness of this treatment for the removal of actinides from Zircaloy cladding to produce a low-level radioactive waste (LLW) cladding product. Analysis of the cladding shows that actinides are present in the cladding at a concentration of about 5000 {eta}Ci/g, which is about 50 times greater than the acceptable transuranium element limit in low level radioactive waste. It appears that the concentration of nitric acid used for this dissolution study (initial concentration 4 M, with 10 M added as the dissolution proceeded) was inadequate to completely digest the UO{sub 2} present in the more » spent fuel. The mass of insoluble material collected from the initial treatments with nitric acid, 340 g, was much higher than expected, and analysis of this insoluble residue showed that it contained at least 200 g U. « less
Authors: ;
Publication Date:
OSTI Identifier:OSTI ID: 962686
Report Number(s):SRNL-STI-2009-00496
Journal ID: ISSN 0029-5450; NUTYBB; TRN: US0902920
DOE Contract Number:DE-AC09-08SR22470
Resource Type:Journal Article
Resource Relation:Journal Name: Nuclear Technology
Research Org:SRS
Sponsoring Org:DOE
Country of Publication:United States
Language:English
Subject: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 36 MATERIALS SCIENCE; ACTINIDES; DISSOLUTION; LOW-LEVEL RADIOACTIVE WASTES; NITRIC ACID; NUCLEAR FUELS; PROCESSING; RADIOACTIVE WASTES; REMOVAL; RESIDUES; SOLVENT EXTRACTION; SPENT FUELS; TRANSURANIUM ELEMENTS; ZIRCALOY; ZIRCALOY 2