The nuclear physics codes for Low-Enriched (LEU) HTR fuel can be verified and adjusted with measurements at the test HTR reactors in Japan (HTTR) and in China (HTR-10).
Additional information will be available from the critical facility PROTEUS in Switzerland. The core analyses with different codes will allow determining temperature coefficients and control rod worth for block and pebble bed type HTR with LEU fuel for safety evaluation and design. Plutonium extracted fro m spent LWR MOX is considered as an attractive HTR- fuel cycle to reduce the growing stockpiles of civil Plutonium.
HTR core analysis will be made for this symbiosis of LWR and HTR. Special treatments for purification of contaminated carbonaceous material from the core structures are intended to improve the disposal or re-use. Data for long-term geochemical modelling of directly disposed spent HTR fuel will be generated by leaching tests on the matrix, coating and kernels of fuel elements.
Funding SchemeCSC - Cost-sharing contracts
CA20 1PG Seascale
91191 Gif Sur Yvette
78141 Velizy Villacoublay
2629 JB Delft
WA16 8QZ Knutsford
1755 ZG Petten