ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
May 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
June 2026
Nuclear Technology
April 2026
Fusion Science and Technology
Latest News
Nuclear Energy Strategy announced at CNA2026
At the Canadian Nuclear Association Conference (CNA2026) in Ottawa, Ontario, on April 29, Minister of Energy and Natural Resources Tim Hodgson announced that Natural Resources Canada (NRCan) is developing a new Nuclear Energy Strategy for the country. The strategy, which is slated to be released by the end of this year, will be based on four objectives: 1) enabling new nuclear builds across Canada, 2) being a global supplier and exporter of nuclear technology and services, 3) expanding uranium production and nuclear fuel opportunities, and 4) developing new Canadian nuclear innovations, including in both fission and fusion technologies.
Pierre Benoist
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 85-94
Technical Paper | doi.org/10.13182/NSE67-A17245
Articles are hosted by Taylor and Francis Online.
A general expression allowing the calculation of the influence on cell factors of an anisotropic component of the scattering law in a given medium is established in the framework of the integral transport theory. This expression is applied to the calculations of the thermal utilization, fast fission factor, and diffusion coefficients. In the case of the thermal utilization, the effect of the anisotropic scattering in the moderator can be taken into account by a rigorous correction whatever the cell; this correction coincides with the classical transport correction only for widely spaced lattices, and still with some restrictions; for closely packed lattices the transport correction has no theoretical justification, and seriously underestimates the effect. In the fuel, the transport correction is no more theoretically justified, although it leads to good results for rather large rods; a very simple formula is established from the general expression, allowing the calculation of the correction to f, without using the transport cross section. This formula leads, for all the rod diameters considered, to results in very good agreement with referenced values obtained by the S8 method. An analogous formula for the fast-fission factor is established.