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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
Standards Program
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.
Paul W. Humrickhouse, Paul P. H. Wilson
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 166-175
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3754
Articles are hosted by Taylor and Francis Online.
A model of the University of Wisconsin Nuclear Reactor has been developed using MCNP5. Benchmarking of the model has centered on available reactor operations data from the original loading of the current TRIGA Fuel Life Improvement Program core, including control element differential worth curves and axial flux maps. By simulating the experimental measurement procedure for control element worth, integral worth values obtained for three control blades are within 6% of measured values. The comparison of simulated and measured axial thermal flux profiles suggests the need to improve the definition of the core temperatures and detailed isotopics. Future plans include modeling full-power (1 MW), high-temperature operation and burnup calculations to obtain current fuel definitions.