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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
2024: The Year in Nuclear—April through June
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from April through May 2024.
Stay tuned for the top stories from the rest of the past year.
Tay-Jian Liu, Yea-Kuang Chan, Yuh-Ming Ferng, Chien-Yeh Chang
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 187-200
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3056
Articles are hosted by Taylor and Francis Online.
The thermal-hydraulic phenomena of inadequate core cooling caused by a cold-leg small-break loss-of-coolant accident (SBLOCA) were investigated experimentally at the Institute of Nuclear Energy Research Integral System Test facility. The experiments were performed under the conditions of different break sizes (0.5 and 2%) in the cold leg followed by failure of the high-pressure injection system. The primary system cooldown is implemented by the secondary-side depressurization. The effectiveness of early initiation of the recovery action on reactor safety and related thermal-hydraulic phenomena are examined. The initiation criterion for recovery action considered here is determined by core water levels instead of core exit temperature based on the current emergency operating procedures. The impact of emergency core-cooling flow bypass phenomenon may significantly deteriorate the effectiveness of the recovery operation for a cold-leg SBLOCA. The results showed that the early initiation of secondary-side depressurization can effectively minimize the risk of core damage by preventing fuel rods from heating up throughout the transient. In addition, the core suffers a rather moderate thermal stress during the cooldown process.