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Division Spotlight
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.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Gary S. Hoovler, M. Neil Baldwin, Ray L. Eng, Fred G. Welfare
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 217-237
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Fuel | doi.org/10.13182/NT80-A32604
Articles are hosted by Taylor and Francis Online.
Close-packed storage of light water reactor (LWR) fuel assemblies is needed to expand the capacity of existing underwater storage pools. This increased capacity is required to store the large volume of spent fuel that arises from prolonged on-site storage. To provide benchmark criticality data in support of this effort, an experimental program sponsored by the U.S. Department of Energy was undertaken. Low-enriched UO2 fuel pins in a water-moderated lattice were used to construct 20 critical assemblies that simulated a variety of close-packed LWR fuel storage configurations. The critical assemblies consisted of nine LWR-type fuel assemblies (clusters) grouped in a radially reflected 3×3 array. Both the spacing and material between the fuel clusters were varied to provide numerous critical configurations. All pertinent data for each critical assembly are documented in sufficient detail to validate calculational methods according to the American National Standards Institute standard N16.9-1975. Criticality calculations using the Monte Carlo code KENO IV were performed for comparison with the experimental data. The comparison shows that the calculational model underestimates keff when separation between fuel clusters is >1 pin pitch (1.64 cm), and that the degree of underestimation increases as the spacing widens.