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Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
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.
Martin Knight, Paul Bryce, Sheldon Hall
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 398-408
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A19428
Articles are hosted by Taylor and Francis Online.
This paper describes a method of analyzing pressurized water reactor UO2/mixed oxide (MOX) cores with the lattice code WIMS and the reactor code PANTHER. "Embedded supercells," run within the reactor code, are used to correct the standard methodology of using two-group smeared data from single-assembly (SA) lattice calculations. In many other codes the weakness of this standard approach has been improved for MOX by imposing a more realistic environment in the lattice code or by improving the sophistication of the reactor code. In this approach an intermediate set of calculations is introduced, leaving both lattice and reactor calculations broadly unchanged.The essence of the approach is that the whole core is broken down into a set of embedded supercells, each extending over just four quarter assemblies, with zero leakage imposed at the assembly midlines. Each supercell is solved twice, first with a detailed multigroup pin-by-pin solution and then with the standard SA approach. Correction factors are defined by comparing the two solutions, and these can be applied in whole-core calculations.The restriction that all such calculations be modeled with zero leakage means that they are independent of each other and of the core-wide flux shape. This allows parallel precalculation for the entire cycle once the loading pattern has been determined, in much the same way that SA lattice calculations can be precalculated once the range of fuel types is known.Comparisons against a whole-core pin-by-pin reference demonstrates that the embedding process does not introduce a significant error, even after burnup and refueling. Comparisons against a WIMS reference demonstrate that a pin-by-pin multigroup diffusion solution is capable of capturing the main interface effects.This therefore defines a practical approach for achieving results close to lattice code accuracy but broadly at the cost of a standard reactor calculation.