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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.
Meeting Spotlight
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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Become a knowledge manager at UWC 2024
The American Nuclear Society is now accepting applications for knowledge managers to work during the 2024 Utility Working Conference and Vendor Technology Expo. This year’s UWC, “Nuclear Momentum: Advancing Our Clean Energy Future,” will be held August 4–7, 2024, at the JW Marriott Marco Island Beach Resort on Marco Island, Fla.=
Ernestas Narkūnas, Artūras Šmaižys, Povilas Poškas, Audrius Šimonis, Valerij Naumov, Dmitrij Ekaterinichev
Nuclear Technology | Volume 208 | Number 12 | December 2022 | Pages 1876-1889
Technical Paper | doi.org/10.1080/00295450.2022.2092367
Articles are hosted by Taylor and Francis Online.
This paper presents an evaluation of the gamma-radiation shielding capabilities of the CONSTOR® RBMK-1500/M2 cask dedicated for the storage of spent nuclear fuel at the Ignalina Nuclear Power Plant in Lithuania. This cask is of a new design with increased capacity compared to the older CONSTOR RBMK-1500 and CASTOR RBMK-1500 casks and new facility for their interim storage has been installed. “Hot tests” conducted at this new interim storage facility included dose rate measurements of the CONSTOR RBMK-1500/M2 casks that were loaded with particular sets of spent nuclear fuel half-assemblies and transferred to the facility for subsequent interim storage. Having actual data on the spent nuclear fuel half-assemblies that were loaded into a particular cask, gamma dose rate modeling of that CONSTOR RBMK-1500/M2 cask (namely, cask ID 153) was performed. Modeling was performed using the MCNP (based on the stochastic mathematical method) and the VISIPLAN and MicroShield (both based on the deterministic mathematical method) computer codes. The obtained modeling results were compared between the different codes and with the measurement results. The performed analysis revealed that modeled gamma dose rates are in good agreement for all analyzed codes, although agreement with the measurements is to some extent less.