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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Senate committee hears from energy secretary nominee Chris Wright
Wright
Chris Wright, president-elect Trump’s pick to lead the U.S. Department of Energy, spent hours today fielding questions from members of the U.S. Senate’s committee on Energy and Natural Resources.
During the hearing, Wright—who’s spent most of his career in fossil fuels—made comments in support of nuclear energy and efforts to expand domestic generation in the near future. Asked what actions he would take as energy secretary to improve the development and deployment of SMRs, Wright said: “It’s a big challenge, and I’m new to government, so I can’t list off the five levers I can pull. But (I’ve been in discussions) about how to make it easier to research, to invest, to build things. The DOE has land at some of its facilities that can be helpful in this regard.”
H. Gerwin, W. Scherer
Nuclear Science and Engineering | Volume 97 | Number 1 | September 1987 | Pages 9-19
Technical Paper | doi.org/10.13182/NSE87-A23491
Articles are hosted by Taylor and Francis Online.
A simple method has been developed for treating large cylindrical empty and rodded void regions in high-temperature gas-cooled reactors with each existing diffusion code. The cavity is treated as a diffusion region with zero reaction cross sections. Only diffusion constants, found by an optimization process, are used. Verification of this model is done by comparing results with transport solutions for identical problems. Very good agreement is attained when anisotropic diffusion is foreseen in the diffusion code. Even with isotropic diffusion, however, eigenvalues and rod reactivities proved to be acceptable. This treatment yields usual diffusion running times and allows three-dimensional calculations.