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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Fabrication milestone for INL’s MARVEL microreactor
A team from Idaho National Laboratory and the Department of Energy’s Office of Nuclear Energy (DOE-NE) recently visited Carolina Fabricators Inc. (CFI), in West Columbia, S.C., to launch the fabrication process for the primary coolant system of the MARVEL microreactor. Battelle Energy Alliance (BEA), which manages INL, awarded the CFI contract in January.
Franklyn M. Clikeman, Sai-Chi Mo, Karl O. Ott, Gary Alan Harms, H. P. Chou, R. H. Johnson
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 341-352
Technical Paper | Analyse | doi.org/10.13182/NT85-A33731
Articles are hosted by Taylor and Francis Online.
Six capture rates, five fission rates, and one inelastic scattering rate have been measured as a function of radius in the blanket of the Fast Breeder Blanket Facility, a facility designed to simulate the transport of neutrons in fast reactor blankets. The measured reaction rates were compared with the reaction rates obtained from a typical two-dimensional calculation. The calculated reaction rates agree well with the measurements at the inside of the blanket but diverge from the measurements with increasing blanket penetration. Two effects were found to account for all of the differences between the calculated and measured reaction rates. First, a quantity approximately equal to the neutron number density decreases more rapidly across the blanket in the calculations than the measurements would indicate. Second, a self-shielding transition effect was noticeable around the converter/blanket interface. Furthermore, a mutual shielding effect between 238U cross-section resonances and detector foil resonances caused additional differences between the measurements and calculations of three capture rates for materials commonly used in neutron dosimetry experiments. The experimental techniques and the results of the reaction rate measurements are presented in detail, including a theoretical foil correction (by means of integral transport theory) that replaces the previously used experimental correction. This work completes and complements earlier experiments, comparisons, and interpretations.