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 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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!
Latest Magazine Issues
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
Latest News
NEUP honors young ANS members with R&D awards
Each year, the Department of Energy’s Nuclear Energy University Program (NEUP) recognizes graduate and undergraduate students for their innovative nuclear energy research. The winners of the Innovations in Nuclear Energy Research and Development Student Competition (INSC) receive honoraria along with travel and conference opportunities, including the chance to present their publications at the annual American Nuclear Society Winter Conference & Expo.
Bertram Wolfe, David Fischer
Nuclear Science and Engineering | Volume 5 | Number 1 | January 1959 | Pages 5-10
Technical Paper | doi.org/10.13182/NSE59-A27321
Articles are hosted by Taylor and Francis Online.
The perturbation approach to control element evaluation is extended from the work presented in a previous paper. A two-group second-order perturbation expression for control element worth is obtained. This has, as its starting point, the unperturbed fast flux but considers the depression in the thermal flux caused by the control element and then, in turn, considers the perturbation on the fast flux caused by the perturbed thermal flux. Finally, the effect of the perturbed fast flux on the thermal flux is evaluated. It is shown that this process, if continued, converges to the correct answer. The perturbation results are compared to experiments for the case of a weak rod in the reflector region of the Bulk Shielding Reactor. The perturbation results are also compared to exact two-group calculations for a cylindrical rod on the axis of a bare cylindrical reactor. In both cases, excellent agreement is obtained.