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The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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NRC begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
R. A. Brown, C. Blahnik, A. P. Muzumdar
Nuclear Science and Engineering | Volume 88 | Number 3 | November 1984 | Pages 425-435
Technical Paper | doi.org/10.13182/NSE84-A18596
Articles are hosted by Taylor and Francis Online.
Loss-of-coolant accident (LOCA) analysis for a Canada Deuterium Uranium (CANDU) reactor considers a wide range of postulated break sizes and locations in the heat transport piping. Coincident failure of the emergency coolant injection system to operate on demand must also be considered. The unique features of the CANDU core and heat transport system, and how these features affect the response of the system to a LOCA, are described. The possible range of behavior of the fuel and fuel channels following a LOCA is discussed in terms of the maximum fuel temperatures that could occur and also in terms of the potential for breaching the core pressure boundary (in the case of CANDU, this boundary comprises a large number of horizontal pressure tubes, each containing horizontal fuel bundles). It is concluded that fuel temperatures remain well below the UO2 melting temperatures and that the integrity of the pressure tubes is maintained for all postulated LOCAs.