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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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.”
R. N. Hill, K. O. Ott, J. D. Rhodes
Nuclear Science and Engineering | Volume 103 | Number 1 | September 1989 | Pages 25-36
Technical Paper | doi.org/10.13182/NSE89-A23657
Articles are hosted by Taylor and Francis Online.
Analytical exploratory investigations indicate that transition effects such as streaming cause a considerable spatial variation in the neutron spectra across resonances; streaming leads to opposite effects in the forward and backward directions. The neglect of this coupled spatial/angular variation of the transitory resonance spectra is an approximation that is common to all current group constant generation methodologies. This paper aims at an accurate description of the spatial/angular coupling of the neutron flux across isolated resonances. It appears to be necessary to differentiate between forward- and backward-directed neutron flux components or even to consider components in narrower angular cones. The effects are illustrated for an isolated actinide resonance in a simplified fast reactor blanket problem. The resonance spectra of the directional flux components φ+ and φ‾, and even more so the 90-deg cone components, are shown to deviate significantly from the infinite medium approximation, and the differences increase with penetration. The changes in φ+ lead to a decreasing scattering group constant that enhances neutron transmission; the changes in φ‾ lead to an increasing group constant inhibiting backward scattering. Therefore, the changes in the forward- and backward-directed spectra both lead to increased neutron transmission. Conversely, the flux (φ = φ + + φ‾) is shown to agree closely with the infinite medium approximation both in the analytical formulas and in the numerical solution. The directional effects cancel in the summation. Therefore, flux-weighted (“diffusion theory”) group constants cannot accurately describe the transmission problem, even using transport theory, as the use of flux weighting eliminates the significant directional effects. The forward- and backward-directed flux components are used as weighting spectra to illustrate the group constant changes for a single resonance. Results indicate that these changes have a magnitude that can likely account for calculational underpredictions observed in fast reactor blanket regions.