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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.
E. T. Cheng, T. Y. Sung, D. K. Sze
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 362-368
Technical Paper | Reactor | doi.org/10.13182/NT77-A31800
Articles are hosted by Taylor and Francis Online.
The neutronics and photonics of the gas-carried Li2O blanket have been studied. The blankets studied consist of 20 to 30% Li2O solid particles and 2% Type 316 stainless-steel structural material in volume. The Li2O blanket can achieve a high tritium breeding ratio without a neutron multiplier due to its high lithium atom density. The effects of the design variations on the tritium breeding ratio and total nuclear heating are summarized as follows: