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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
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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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Latest News
Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
Patrick Dumaz
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 946-955
Technical Paper | TMI-2: Decontamination and Waste Management / Nuclear Safety | doi.org/10.13182/NT89-A27688
Articles are hosted by Taylor and Francis Online.
Within the framework of the Three Mile Island Unit 2 Analysis Exercise, the calculation of phases I and 2 of the accident (0 to 174 min) was performed with the computer code CA THARE 1 and with a preliminary version of CATHARE 1/ICARE. The initial transient (0 to 30 min) is accurately predicted by CATHARE. From the thermal-hydraulic point of view, the remainder of phase 1 has also been very well simulated, even though for the overall problem, this particular part of phase 1 did not prove to be nearly as difficult. The analysis of phase 2 is limited because the computer code does not calculate material relocation. Nevertheless, cladding ballooning and cladding oxidation seem to be correctly predicted.
