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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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.
William J. Kovacs, Karl Bongartz, Dan T. Goodin
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 344-354
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33580
Articles are hosted by Taylor and Francis Online.
A Triso-coated particle stress model was used to describe pressure vessel failure in high-temperature gas-cooled reactor fuel particles. Two separate failure modes were treated, namely, category I, which applies to standard particles characterized by a load-bearing silicon carbide (SiC) layer and instantaneous pyrolytic carbon (PyC) and SiC failure, and category II, which applies to particles with a defective SiC layer incapable of supporting a tensile load. Closed-form solutions, which describe PyC and SiC coating layer stresses as a function of irradiation conditions and particle geometry, were adapted to Monte Carlo calculational routines. The PyC and SiC stresses were calculated for a large number (104 to 106) of particles, and particle failure was predicted to occur when the calculated coating layer tensile stresses exceeded either the SiC (category I failure) or PyC (category II failure) fracture lengths. Model predictions are generally consistent with irradiation test results and serve as a useful guide for particle design optimization studies and in-core fuel performance evaluations.