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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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.
M. CANTWELL, M. GOLDSMITH
Nuclear Science and Engineering | Volume 12 | Number 4 | April 1962 | Pages 490-497
Technical Paper | doi.org/10.13182/NSE62-A26096
Articles are hosted by Taylor and Francis Online.
Measured fast fission activations of depleted U238 foils in thin clean critical slabs are compared with theoretical predictions made using the P-1 and P-3 approximations. Various methods of analyzing fast activation experiments are considered. Finally, the effect of the P-3 approximation in the fast groups on the thermal flux is studied by comparing Mn wire activations out to 50 cm in the reflector of a thin clean critical slab with several theoretical calculations. It is found, as would be expected, that the deviations of the calculated P-1 activations from experiment increase as the observer moves farther out into the reflector. The use of the P-3 approximation gives marked improvement. As regards eigenvalues, experience in the analysis of thin clean critical slabs with highly enriched fuel and metal-to-water volume ratios from 1 to 1.7 indicates that use of the P-3 approximation in the first few fast groups results in an increase in eigenvalue of more than a per cent.