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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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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.
K. S. Smith
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 451-458
Technical Paper | doi.org/10.13182/NSE82-A20286
Articles are hosted by Taylor and Francis Online.
An investigation of first-order perturbation (FOP) methods for computing sample worths has been performed. It is demonstrated that conventional cell homogenization methods introduce errors into FOP reactivity calculations because the intracell structure of adjoint fluxes is neglected. These errors are such that the conventional FOP reactivity expression is not accurate to first order, even in the limit of infinitesimal perturbations. A method for avoiding such approximations is introduced and applied to the calculation of small sample worths in plate-type fast reactor critical assemblies. It is demonstrated that errors introduced by real flux weighting of cross sections are such that homogenized FOP reactivity calculations overestimate fissile material worths in several critical assemblies by 5 to 10%. It is shown that these errors arise because of the heterogeneous nature of plate-type critical assemblies, and when appropriate reactivity calculations (which account for spatial heterogeneity of adjoint fluxes) are performed, a significant fraction of the long-standing central worth discrepancy is eliminated.