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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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2025 ANS Annual Conference
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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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Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Tay-Jian Liu, Chien-Hsiung Lee
Nuclear Technology | Volume 146 | Number 3 | June 2004 | Pages 257-266
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3504
Articles are hosted by Taylor and Francis Online.
Two experiments for a small-break loss-of-coolant accident on a pressurizer top were conducted at the Institute of Nuclear Energy Research (INER) Integral System Test (IIST) facility to investigate the thermal-hydraulic behavior of a passive core cooling system (PCCS) in a Westinghouse pressurized water reactor (PWR). The test results are compared with previous IIST tests under the same initial and boundary conditions for a power-operated relief valve (PORV) stuck-open incident. The objectives of this study are to understand the key thermal-hydraulic phenomena associated with the PCCS and to compare the effectiveness of accident management with or without the PCCS. The break sizes are scaled down based on one and all three fully opened PORVs for a conventional PWR without the PCCS. This paper identifies the key phenomena commonly observed and the phenomena unique to a PWR with a PCCS.
