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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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
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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
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.
Hisao Yamakoshi
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 152-180
Technical Paper | doi.org/10.13182/NSE84-A17709
Articles are hosted by Taylor and Francis Online.
By introducing a concept of shielding characteristics, a new method is proposed for shielding calculations of spent fuel shipping casks. The method separates ordinary shielding calculation into two steps, one calculates the radiation current leaking from the unshielded cavity region. The other method synthesizes the radiation dose rate outside the cask arising from the leaked current, the response functions for the radiation dose rate at the outer cask surface, and the functions for the radiation current reflected from the inner surface of the cask wall. In the synthesis, the effect of the coupling of the currents reflected between the cask wall and the cavity region is taken into account. The validity of the proposed method is confirmed by applying the method to an analysis of the measured data obtained for a CRIEPI cask. Response functions, the established characteristic functions for radiation shielding capabilities, are calculated for several typical actual casks. Calculated results are summarized for the convenience of applying the proposed method to actual cases. The merits of the present study are (a) the calculational code of the proposed method deals with only matrix calculations in short-step programming and is suitable for a microcomputer for which input data of characteristic functions are supplied from floppy disks, (b) with large and high-speed computers, one can evaluate radiation dose rates on the outer surface of a given cask in very short machine time and with good accuracy, (c) by application of the characteristic functions, one can extract information that will improve the design of the cask walls to provide more effective shielding by intercomparison of characteristic functions for several types of casks, and (d) one can foresee the influence of changes in the energy spectrum of source radiations on the neutron and the gamma-ray dose rates at the outer cask surface by the rule-of-thumb of superimposing the characteristic functions of the dose rate because they are functions of the incident energies.
