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Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Moltex demonstrates its WATSS fuel recycling process
Advanced reactor company Moltex Energy Canada said it has successfully validated its waste to stable salt (WATSS) process on used nuclear fuel bundles from an unnamed Canadian commercial reactor through hot cell experiments conducted by Canadian Nuclear Laboratories.
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.