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.
Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Mar 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
NRC begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
S. V. G. Menon, D. C. Sahni
Nuclear Science and Engineering | Volume 82 | Number 3 | December 1982 | Pages 359-364
Technical Note | doi.org/10.13182/NSE82-A19397
Articles are hosted by Taylor and Francis Online.
In this Note we treat the problem of resonance absorption in a heterogeneous lattice cell using Fourier transforms. It is shown that the slowing down equations for the fuel and moderator flux, resulting from a flat flux approximation and the rational approximation for the fuel escape probability, get decoupled in the Fourier transform space. This decoupling is achieved without using the normal assumption of narrow resonance approximation for the moderator collision integral, and hence can be viewed as a generalization of the equivalence theorem of resonance absorbtion theory. Using certain ideas from the theory of distributions, we obtain a Fredholm integral equation (FIE) in the transform space. This integral equation with the kernel having a pole at the origin is similar to that obtained in the Fourier transform method for the homogeneous medium problem developed in our recent work. It is shown that the tem-perature-dependent resonance integrals and Doppler coefficients can be evaluated by converting the FIE to a matrix equation using the composite trapezoidal rule. Numerical results are presented to demonstrate the accuracy of the method.