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The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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WIPP’s SSCVS: A breath of fresh air
This spring, the Department of Energy’s Office of Environmental Management announced that it had achieved a major milestone by completing commissioning of the Safety Significant Confinement Ventilation System (SSCVS) facility—a new, state-of-the-art, large-scale ventilation system at the Waste Isolation Pilot Plant, the DOE’s geologic repository for defense-related transuranic (TRU) waste in New Mexico.
R. N. Hwang, L. B. Miller
Nuclear Science and Engineering | Volume 42 | Number 2 | November 1970 | Pages 179-190
Technical Paper | doi.org/10.13182/NSE70-A19499
Articles are hosted by Taylor and Francis Online.
This paper discusses the statistical uncertainties of the self-shielded group cross section and its temperature derivative associated with the use of the biased selection technique where resonances are chosen to match the observed value of the unshielded cross section. Since the self-shielded group cross section can always be pictured as a superposition of an infinitely dilute term and a self-shielding term, the problem amounts to the estimation of the conditional variances of the self-shielding term and its temperature derivative for any given value of the infinitely dilute cross section. A semianalytical method based on the NR-approximation has been developed to estimate these conditional variances. Both qualitative and quantitative discussions are given for cases of 239Pu and 238U under various physical conditions.