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The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Moltex demonstrates its WATSS fuel recycling process
Advanced reactor company Moltex Energy Canada said it has successfully validated its waste to stable salt (WATSS) process on used nuclear fuel bundles from an unnamed Canadian commercial reactor through hot cell experiments conducted by Canadian Nuclear Laboratories.
J. J. Mcinerney
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 392-397
Technical Paper | doi.org/10.13182/NSE63-A17387
Articles are hosted by Taylor and Francis Online.
Some aspects of the relation between the energy dependence of the scattering cross section and the spatial distribution of neutrons slowing down in a hydrogeneous moderator are discussed. The neutron population in an infinite medium is analyzed using the mean square slowing down distance, , as a measure of its spatial extent. It is shown that, contrary to what is perhaps expected, the neutron population in many cases is distributed closer to its source with decreasing energy. In the analysis of this behavior it is found that diffusion theory may in some cases be expected to give good results close to the spatial position of the source. A correction term is also found for the “first flight” transport kernel often used in practical calculations.