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Title: Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction

The aim of the research presented here was to identify the chemical form of 14C in irradiated graphite. A greater understanding of the chemical form of this longest-lived isotope in irradiated graphite will inform not only management of legacy waste, but also development of next generation gas-cooled reactors. Approximately 250,000 metric tons of irradiated graphite waste exists worldwide, with the largest single quantity originating in the Magnox and AGR reactors of UK. The waste quantity is expected to increase with decommissioning of Generation II reactors and deployment of Generation I gas-cooled, graphite moderated reactors. Of greatest concern for long-term disposal of irradiated graphite is carbon-14 14C, with a half-life of 5730 years.
Authors:
; ;
Publication Date:
OSTI Identifier:
1154738
Report Number(s):
DOE/NEUP--09-844
TRN: US1500346
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Research Org:
Idaho State Univ., Pocatello, ID (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE). Nuclear Energy University Programs (NEUP)
Contributing Orgs:
Furnaces Nuclear Applications Grenoble (FNAG), Grenoble (France); Idaho National Lab. (INL), Idaho Falls, ID (United States); Univ. of Manchester (United Kingdom)
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; CARBON 14; GRAPHITE; GCR TYPE REACTORS; RADIOACTIVE WASTES; MAGNOX TYPE REACTORS; REMOVAL; RADIOACTIVE WASTE MANAGEMENT; CHEMISTRY; PROGRESS REPORT