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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 Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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
New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
D. E. Beller, K. O. Ott, W. K. Terry
Nuclear Science and Engineering | Volume 97 | Number 3 | November 1987 | Pages 175-189
Technical Paper | doi.org/10.13182/NSE87-A23500
Articles are hosted by Taylor and Francis Online.
A new conceptual design of a fusion reactor blanket simulation facility has been developed. This design follows the principles that have been successfully employed in the Purdue Fast Breeder Blanket Facility (FBBF), where experiments have resulted in the discovery of substantial deficiencies in neutronics predictions. With this design, discrepancies between calculation and experimental data can be nearly fully attributed to calculation methods because design deficiencies that could affect results are insignificant. The conceptual design of this FBBF analog, the Fusion Reactor Blanket Facility, is presented. Essential features are the cylindrical geometry and a distributed line source of 14-MeV neutrons with a cosine-shaped intensity distribution. The source design consists of a deuteron beam sweeping over an elongated titanium-tritide target. To predict the character of the neutron flux this source will produce, neutronics analyses were performed. Predictions for two- and one-dimensional calculations are compared for two blanket compositions. Expected deviations from one-dimensional predictions, which are due to source anisotropy and blanket asymmetry, are shown to be minimal. Therefore, one-dimensional calculations can be performed in fine detail as a basis for the generation of accurate coarse group constants for two-dimensional predictions. The proposed design of this fusion blanket facility should allow straightforward interpretation of experimental results in terms of computational and data deficiencies.