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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
G7 pledges support for nuclear at Italy meeting
The Group of Seven (G7) recommitted its support for nuclear energy in the countries that opt to use it at a Ministerial Meeting on Climate in Italy last month.
In a statement following the April meeting, the group committed to support multilateral efforts to strengthen the resilience of nuclear supply chains, referencing the goal set by 25 countries during last year’s COP28 climate conference in Dubai to triple global nuclear generating capacity by 2050.
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.