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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
A. Abou-Sena, A. Ying, M. Youssef, M. Abdou
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 211-215
Tritium, Safety, and Environment | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8904
Articles are hosted by Taylor and Francis Online.
The Quarter Port Submodule (QPS) was proposed as a Solid Breeder (SB) Test Blanket Module under the US program of the SB blankets. The QPS features layer configuration, in its left half, where the SB pebble beds are parallel to the first wall and edge-on configuration, in its right half, where the SB pebble beds are perpendicular to the first wall. The objective of this study is to investigate: (i) the QPS thermal profile under steady state conditions and ITER transient loads, and (ii) the impact of the interface conductance h on the QPS thermal profile. In addition the effect of lack of contact, at the SB pebbles/structure interface, on the QPS thermal profile is presented. The results of the steady state cases showed that h has a significant impact on the QPS thermal profile. The QPS transient analysis provided results on: (i) QPS thermal profile under a pulse length of 400s, (ii) burning time required for reaching the equilibrium temperatures, and (iii) time needed to cool the QPS. In the cases of lack of contact, the maximum temperature of the SB pebble beds exceeded the SB temperature limit, which may cause sintering of the pebbles and consequently inhibit the tritium release.