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Division Spotlight
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.
Meeting Spotlight
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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Indrajeet Singh, S. B. Degweker, Amod Kishore Mallick, Anurag Gupta
Nuclear Science and Engineering | Volume 193 | Number 8 | August 2019 | Pages 868-883
Technical Paper | doi.org/10.1080/00295639.2019.1576453
Articles are hosted by Taylor and Francis Online.
In a recent paper, we described the development of a method for calculating exact collision probabilities between different regions (namely, fuel kernels, graphite matrix, moderator, and coolant) of a lattice cell of a high temperature reactor (HTR) of the pebble bed variety. The method was shown to adequately represent the double heterogeneity in such reactors. In the present paper, we use some of the results obtained in that paper to construct a fast Monte Carlo algorithm for treatment of HTRs. This paper discusses the theoretical basis of the Monte Carlo algorithm, its implementation for the case of a lattice cell with the energy variable treated using a multigroup library, and results obtained. The method can be easily extended to full-core calculations using point cross-section data.
