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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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Remembering Charles E. Till
Charles E. Till
Charles E. Till, an ANS member since 1963 and Fellow since 1987, passed away on March 22 at the age of 89. He earned bachelor’s and master’s degrees from the University of Saskatchewan and a Ph.D. in nuclear engineering from Imperial College, University of London. Till initially worked for the Civilian Atomic Power Department of the Canadian General Electric Company, where he was the physicist in charge of the startup of the first prototype CANDU reactor in Canada.
Till joined Argonne National Laboratory in 1963 in the Applied Physics Division, where he worked as an experimentalist in the Fast Critical Experiments program. He then moved to additional positions of increasing responsibility, becoming division director in 1973. Under his leadership, the Applied Physics Division established itself as one of the elite reactor physics organizations in the world. Both the experimental (critical experiments and nuclear data measurements) and nuclear analysis methods work were internationally recognized. Till led Argonne’s participation in the International Nuclear Fuel Cycle Evaluation (INFCE), and he was the lead U.S. delegate to INFCE Working Group 5, Fast Breeders.
Patrick Jaffke
Nuclear Science and Engineering | Volume 190 | Number 3 | June 2018 | Pages 258-270
Technical Paper | doi.org/10.1080/00295639.2018.1429173
Articles are hosted by Taylor and Francis Online.
We present a self-consistency analysis of fission product yield evaluations. Anomalous yields are determined using a series of simple conservation checks and comparing charge distributions with common parameterizations. The summed average prompt neutron multiplicity for both products as a function of the heavy product mass is derived directly from the independent fission product yields with a procedure utilizing average charge conservation. This procedure is validated with Monte Carlo simulations of the de-excitation of the fission fragments in a Hauser-Feshbach statistical decay framework. The derived is compared with experimental data, when available, and then used to determine the prompt neutron multiplicity for the various evaluations. The propagated errors on from the average charge conservation method are significantly lower than the simple summation rules, which reveals that some evaluations are inconsistent with prompt neutron data. We propose possible solutions to remedy the observed inconsistencies and identify sources of the observed differences in between the various evaluation libraries.