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.
Bertram Wolfe, David L. Fischer
Nuclear Science and Engineering | Volume 4 | Number 6 | December 1958 | Pages 785-793
doi.org/10.13182/NSE58-A15498
Articles are hosted by Taylor and Francis Online.
An exact expression for the reactivity effect of a control element placed in a reactor is derived within the limitation of validity of multigroup diffusion theory. The evaluation of the expression requires a knowledge of the flux distributions in the reactor with and without the element (s) inserted. Since the reactivity effect is stated in terms of the flux distribution in the perturbed and unperturbed reactors, one can calculate the effect of a control element if a good estimate for the form of the perturbed flux is made. A first-order perturbation calculation for thermally black control elements is presented. The perturbation calculation assumes that the fast flux is unaffected by the presence of the control element. The results are valid for a reactor in which the neutron age is large compared to the square of the thermal diffusion length and for a control element which is small compared to both the size of the reactor and the square root of the age.