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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
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
Ville Valtavirta, Tuomas Viitanen, Jaakko Leppänen
Nuclear Science and Engineering | Volume 177 | Number 2 | June 2014 | Pages 193-202
Technical Paper | doi.org/10.13182/NSE13-3
Articles are hosted by Taylor and Francis Online.
This paper describes the built-in calculation routines in the reactor physics code Serpent 2 that provide a novel method for solving the coupled problem of the power distribution, temperature distribution, and material property distributions in nuclear fuel elements. All of the coupled distributions are solved during a single simulation with no coupling to external codes. The temperature feedback system consists of three separate built-in parts: an explicit treatment of the thermal motion of target nuclides during the transport calculation, an internal analytic radial temperature profile solver, and internal material property correlations. The internal structure and couplings of the calculation routines are described in detail, after which the results of an assembly-level problem are presented to demonstrate the capabilities and functionality of the system.