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NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Molten salt research is focus of ANS local section presentation
The American Nuclear Society’s Chicago–Great Lakes Local Section hosted a presentation on February 27 on developments at the molten salt research reactor at Abilene Christian University’s Nuclear Energy Experimental Testing (NEXT) Lab.
A recording of the presentation is available on the ANS website.
R. Kladnik, I. Kuscher
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 116-120
Technical Paper | doi.org/10.13182/NSE61-A28055
Articles are hosted by Taylor and Francis Online.
The velocity dependent transport equation for a nonabsorbing semi-infinite medium with no sources is approximately solved by a variational method. A simple trial function, which takes into account the asymptotic behavior of the exact solution, is used to obtain an approximation for the extrapolation distance q∞, and, by iteration, an approximation for the flux distribution. Numerical results are given for a monatomic gaseous medium with the atom mass equal to the neutron mass. The value q∞ = 0.9345 l (∞) is obtained. The velocity distribution of the emerging neutrons shows a hardening effect, corresponding, in the average, to a 14% increase in the neutron temperature.