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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Fusion Science and Technology
Latest News
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
Chikara Konno, Fujio Maekawa, Yukio Oyama, Yujiro Ikeda, Masayuki Wada, Hiroshi Maekawa
Fusion Science and Technology | Volume 34 | Number 1 | August 1998 | Pages 6-17
Technical Paper | doi.org/10.13182/FST98-A49
Articles are hosted by Taylor and Francis Online.
An analysis of the bulk-shielding experiment on Type 316 stainless steel (SS316) for deuterium-tritium neutrons was performed at the Japan Atomic Energy Research Institute Fusion Neutronics Source to validate the nuclear data and transport codes used in the shielding design of the International Thermonuclear Experimental Reactor (ITER). The MCNP-4A and DORT3.1 codes with contemporary nuclear data libraries based on the FENDL/E-1.1 and JENDL Fusion File were used for the analyses. The MCNP calculations with the FENDL/E-1.1 and JENDL Fusion File agree within 30% with the measured data. The DORT calculations with the FENDL/E-1.1 and JENDL Fusion File with an energy structure of 175 neutrons and 42 gamma rays and a self-shielding correction represent the measurements with almost the same accuracy as the MCNP calculations. It is concluded that the uncertainty of the shielding calculation for the bulk-shielding configuration of MCNP-4A and DORT3.1 with the FENDL/E-1.1 and JENDL Fusion File on a 900-mm-thick SS316 shield is within 30%.