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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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Latest News
NNSA awards BWXT $1.5B defense fuels contract
The Department of Energy’s National Nuclear Security Administration has awarded BWX Technologies a contract valued at $1.5 billion to build a Domestic Uranium Enrichment Centrifuge Experiment (DUECE) pilot plant in Tennessee in support of the administration’s efforts to build out a domestic supply of unobligated enriched uranium for defense-related nuclear fuel.
Philip M. Daling, Jay E. Marler, Truong V. Vo, Hanh K. Phan, John R. Friley
Nuclear Technology | Volume 109 | Number 3 | March 1995 | Pages 429-436
Technical Note | Nuclear Reactor Safety | doi.org/10.13182/NT95-A35090
Articles are hosted by Taylor and Francis Online.
The Pacific Northwest Laboratory, under contract to the U.S. Nuclear Regulatory Commission, has conducted an assessment of the values (benefits) and impacts (costs) associated with potential resolutions to Generic Issue 143—“Availability of Heating, Ventilation, and Air Conditioning (HVAC) and Chilled Water Systems.” The key objectives of the study were to (a) identify vulnerabilities related to failures of HVAC, chilled water, and room-cooling systems, (b) develop estimates of room heatup rates and safety-related equipment vulnerabilities following losses of HVAC/room-cooler systems, (c) develop estimates of the core damage frequencies and public risks associated with failures of these systems, (d) develop proposed resolution strategies to this generic issue, and (e) perform a value/impact analysis of the proposed resolutions. Detailed probabilistic risk assessments for four representative plants form the basis for the core damage frequency and public risk calculations. Internally initiated core damage sequences as well as external events were considered. Three proposed resolution strategies were developed for this safety issue, and it was determined that all three were not cost effective. Additional evaluations were performed to develop “generic” insights on potential design-related vulnerabilities and potential high-frequency (> 10−4/reactor-yr) accident sequences that involve failures of HVAC/room-cooling functions. It was concluded that, although high-frequency accident sequences may exist at some plants, these sequences are plant-specific in nature or have been resolved through hardware and/or operational changes. The plant-specific individual plant examinations appear to be an effective vehicle for identification and resolution of these plant-specific anomalies and hardware configurations.