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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
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
NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
Yuzo Fukai
Nuclear Science and Engineering | Volume 13 | Number 4 | August 1962 | Pages 345-354
Technical Paper | doi.org/10.13182/NSE62-A26176
Articles are hosted by Taylor and Francis Online.
In calculating a closely packed lattice, it is well known that one-velocity integral transport theory is the most useful method. Results are briefly presented for calculation of the ratio of moderator to fuel flux in a lattice, , by first and second approximations which have been developed by Corngold. In order to compare these approximations with various other calculating methods, some approximate formulations of a penetrability factor are discussed. After comparing the numerical results from the first and second approximations with the ones of Wachspress, Amouyal, Bengston, and the blackness method, the second approximation is considered to be the best. Consequently the values of the flux ratio in a lattice of fuel cylinders are calculated by using a unit cell method, and the second approximation in the case of a slab lattice which has a mean chord length equivalent to that of the actual lattice, and the results are compared with experiment.