ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
NextGen MURR Working Group established in Missouri
The University of Missouri’s Board of Curators has created the NextGen MURR Working Group to serve as a strategic advisory body for the development of the NextGen MURR (University of Missouri Research Reactor).
V. E. Raevskaya
Nuclear Science and Engineering | Volume 94 | Number 4 | December 1986 | Pages 393-408
Technical Paper | doi.org/10.13182/NSE86-A18349
Articles are hosted by Taylor and Francis Online.
A method for the calculation of the neutron flux in one-group P3 approximation in a reactor polycell with multizone annular clusters is presented. The cluster central zone contains multizone fuel rods. The rod and cluster neutron fluxes are assumed to be azimuthally symmetrical. Four moments in the scattering function are taken into account. The CLUST code has been developed for computing the neutron fluxes in a reactor polycell. Its numerical results are compared with those of the other codes and appear to be in good agreement with them.
