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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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Latest News
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
L. Cantrel
Nuclear Technology | Volume 156 | Number 1 | October 2006 | Pages 11-28
Technical Paper | Reactor Safety | doi.org/10.13182/NT156-11
Articles are hosted by Taylor and Francis Online.
Iodine is a fission product of major importance because volatile species can be formed under severe nuclear reactor accident conditions and may potentially be released into the environment, leading to significant radiological consequences. The CAIMAN program was devoted to studying the radiochemistry of iodine in the reactor containment in the case of a severe accident occurring in a pressurized water reactor; this is a database of prime importance for the validation of codes, namely IODE, which is a module of the integral Accident Source Term Evaluation Code (ASTEC), jointly developed by the Institut de Radioprotection et de Sûreté Nucléaire and the Gesellschaft für Anlagen- und Reaktorsicherheit. These computations are generally used to predict the radiological consequences of such an accident.The experimental program, which ran from 1996 to 2002, concerned 18 experiments in a facility of intermediate scale (300 dm3), where labeled iodine, 131I, was used to perform gamma counting. The CAIMAN tests are here analyzed, and the main experimental observations and trends are described. For each experiment, IODE computations were performed and compared with experimental results in order to assess the possible weak points of the present modeling and to identify key parameters. Broadly speaking, the gaseous concentrations predicted are quite consistent with the experimental ones; the remaining gaps have been identified.