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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
R. C. Kern, M. V. Bonaca
Nuclear Technology | Volume 9 | Number 6 | December 1970 | Pages 796-806
Fuels Cycle | doi.org/10.13182/NT70-A28711
Articles are hosted by Taylor and Francis Online.
Two models which are designed to perform fuel inventory calculations without the use of detailed and expensive computer programs have been developed. The accuracies of these models have been evaluated by comparing results obtained with them to measurements of discharged fuel from the Yankee Rowe reactor. In general, the models predict the 235U depletion to within ±2% of the measured values and the total plutonium production to within ±5% for fuel batches consisting of about 70 fuel assemblies. Uncertainties in the computational results have been ascertained to be about ±2% for the total 235U content and ±3% for the total plutonium production.