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Materials Science & Technology
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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Argonne to investigate Pu chemistry to aid Hanford cleanup
Researchers at the Department of Energy’s Argonne National Laboratory are investigating the details of plutonium chemistry with the goal of aiding the cleanup of the Hanford Site in Washington state. For more than 40 years, reactors located at Hanford produced plutonium for America’s defense program, resulting in millions of gallons of liquid radioactive and chemical waste.
J. Tommasi, E. Dupont, P. Marimbeau
Nuclear Science and Engineering | Volume 154 | Number 2 | October 2006 | Pages 119-133
Technical Paper | doi.org/10.13182/NSE154-119
Articles are hosted by Taylor and Francis Online.
The PROFIL and PROFIL-2 experiments performed in the Phénix demonstration fast reactor irradiated 130 small separate samples containing almost pure isotopes. These highly accurate experiments are a very specific and powerful source of information on the nuclear data of major and minor actinides and several fission products. Their analysis was carried out using the ERANOS-2.0 code system associated to JEFF-3.0 cross-section data, UKFY3.5 fission yield data, and JEF-2.2 decay data. The consistency of the results demonstrates the overall good quality of the actinide nuclear data and experimental techniques used and points out where specific improvement is necessary: fission yields of 235U on neodymium isotopes; integral capture cross sections of 232Th, 233U, 241Pu, 242Pu, and 241Am (and to a lesser extent, 240Pu and 237Np); and branching ratios for 241Am capture. A similar analysis characterizes the degree of accuracy of the integral capture cross sections of 19 fission products. Future plans include the analysis of two new experiments of the same kind, included in the current Phénix experimental program, and the use of a consistent set (cross sections, fission yields, and decay data) of the latest JEFF-3.1 nuclear data files.