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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.
Kenneth W. Burn
Nuclear Technology | Volume 175 | Number 1 | July 2011 | Pages 138-145
Technical Paper | Special Issue on the 16th Biennial Topical Meeting of the Radiation Protection and Shielding Division / Radiation Transport and Protection | doi.org/10.13182/NT11-A12282
Articles are hosted by Taylor and Francis Online.
The Direct Statistical Approach (DSA) was developed in the 1980s and 1990s to optimize Monte Carlo deep penetration (fixed-source) radiation transport calculations. It is based on a detailed mathematical approach to the splitting and Russian roulette problem, independent of, or dependent on, the weight of the particle track. As it relies on splitting and Russian roulette, it is of quite general application and has been employed on a wide variety of problems: reactor shielding, accelerator shielding, accelerator-driven systems, dosimetry, and nuclear medicine. The development of the DSA culminated in the inclusion of a multiresponse capability. Over the last 10 years this capability has completely supplanted the single-response version of the DSA. It is considered that the multiresponse capability represents a significant advance. Examples of its use are illustrated. The DSA is currently undergoing a substantial update. The state of the art of the new code is given.