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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Former NRC commissioners lend support to efforts to eliminate mandatory hearings
A group of nine former nuclear regulatory commissioners sent a letter Wednesday to the current Nuclear Regulatory Commission members lending support to efforts to get rid of mandatory hearings in the licensing process, which should speed up the process by three to six months and save millions of dollars.
Leah Spradley, Mark Abkowitz, James H. Clarke
Nuclear Technology | Volume 165 | Number 2 | February 2009 | Pages 209-222
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT09-A4087
Articles are hosted by Taylor and Francis Online.
This paper describes the development and use of an integrated model to explore the impact of design parameters and operational decisions on storage and transportation aspects of the preclosure activity period for the potential repository at Yucca Mountain (YM), Nevada. The model provides an opportunity to perform analyses of various YM preclosure "scenarios." Storage and transportation aspects of the preclosure system are evaluated with the goal of identifying important design parameters and understanding system interactions, thereby providing a tool to recognize trade-offs and dependencies between storage demands at the waste generation sites and the repository.This application of the model explores changes in assumptions regarding the following parameters: (a) year the transportation, aging, and disposal (TAD) canister becomes available; (b) year that YM opens; (c) thermal limit for emplacement; (d) thermal limit for transportation; and (e) utility strategies for selecting assemblies for dry storage loading.The response variables measured are (a) dry storage containers loaded because of lack of capacity in the spent nuclear fuel pools, (b) TAD canisters that could potentially be loaded before YM opens (assuming utilities begin using the TAD canister as soon as it is commercially available), (c) pools from which shipments to YM originate each year, (d) years aboveground aging is required at YM, and (e) containers in the aging facility at YM each year.Results indicate that allowing utilities to trade allocations, prioritizing the trading based on least remaining capacity in the spent nuclear fuel pools, could reduce dry storage demands at the utility sites, decrease the number of pools making shipments each year, and increase the efficiency of the transportation system. This type of prioritization for allocations can provide these improvements without adversely impacting the required aboveground aging at YM in the case that younger fuel is sent first. Consequently, there may be incentive for utilities to negotiate the trading of allocations if they wish to reduce their expected dry storage demands after shipments commence to YM.