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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
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
S. Rauck, R. Sanchez, I. Zmijarevic, M. Nobile
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 73-83
Technical Paper | doi.org/10.13182/NSE00-A2126
Articles are hosted by Taylor and Francis Online.
Through the introduction of appropriate boundary conditions, the use of multigroup albedos permits one to concentrate the numerical effort of solving the transport equation in only the domain of interest, thus reducing computational requirements. Multigroup albedos that are representative of an external medium can be calculated via independent transport calculations and collapsed for use in a few-group three-dimensional transport calculation. The multigroup albedo method is developed and applied to the calculation of the Orphée research reactor. Numerical comparisons between full-core two-dimensional transport calculations and two-dimensional transport calculations performed with multigroup albedos show why the method is interesting. The axial power distribution obtained from a three-dimensional transport calculation with multigroup albedos precisely matches measured experimental values, while results from three-dimensional full-core diffusion calculations give unacceptable errors.