ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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Nuclear Science and Engineering
February 2025
Nuclear Technology
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Latest News
Feinstein Institutes to research novel radiation countermeasure
The Feinstein Institutes for Medical Research, home of the research institutes of New York’s Northwell Health, announced it has received a five-year, $2.9 million grant from the National Institutes of Health to investigate the potential of human ghrelin, a naturally occurring hormone, as a medical countermeasure against radiation-induced gastrointestinal syndrome (GI-ARS).
Sadia Khalid, Idrees Ahmad, Awais Zahur
Nuclear Technology | Volume 205 | Number 9 | September 2019 | Pages 1175-1184
Technical Paper | doi.org/10.1080/00295450.2019.1580530
Articles are hosted by Taylor and Francis Online.
The long-term, safe, and reliable operation of a reactor coolant pump is vital for the safety of a nuclear reactor. In the case of a station blackout or power failure to the pump, the inertia of rotating parts of the pump should provide sufficient pumping capacity or flow rate to remove decay heat to ensure the safety of the reactor. An accurate flow coastdown analysis is required for the design and manufacture of reactor coolant pumps. In this paper a mathematical model is formulated to study flow coastdown of CHASNUPP-2, which is a pressurized water reactor. Frictional losses in the pump are also incorporated in the model to get accurate results. Two important parameters of the model are inertia of the pump impeller and inertia of the coolant, which are related to each other in the form of effective energy ratio. The effective energy ratio is made variable in order to accurately model the flow coastdown transient. The model is solved numerically to get flow coastdown curves and the comparison of the theoretical and experimental results shows a good agreement between them.