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Division Spotlight
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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Keiichiro Tsuchihashi, Yorio Gotoh
Nuclear Science and Engineering | Volume 58 | Number 2 | October 1975 | Pages 213-225
Technical Paper | doi.org/10.13182/NSE75-A28224
Articles are hosted by Taylor and Francis Online.
The effective resonance absorption of coated particles, which are embedded in a graphite matrix, is studied. The effect of a random arrangement of particles on the resonance integral is examined using the radial distribution function derived from the Percus-Yevick equation. A differential equation is proposed to obtain the neutron-beam current from a source particle in a medium in which the distribution function of coated particles is specified. By the use of the neutron beam current and the distribution function as the weight, the fuel-to-fuel collision probability is defined. This collision probability is applied to a RICM-type resonance integral code. The depression of the resonance integral of 238U due to grain structure amounts 5% in a design study of the multi-purpose high-temperature gas-cooled reactor (HTGCR) at the Japan Atomic Energy Research Institute. The applicabilities of the spherical cell model and of the collision probability in the high-dilution approximation of Lane et al. are tested. These simple procedures give satisfactory results for the treatment of microscopic heterogeneity in the range of the HTGCR design.
