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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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The when, where, why, and how of RIPB design
The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) held another presentation in its monthly Community of Practice (CoP) series.
Watch the full webinar here.
Ayumi Abe, Hidehiro Tobita, Nobuaki Nagata, Koji Dozaki, Hideki Takiguchi
Nuclear Science and Engineering | Volume 149 | Number 3 | March 2005 | Pages 312-324
Technical Paper | doi.org/10.13182/NSE149-312
Articles are hosted by Taylor and Francis Online.
Hydrogen injection has been applied as a preventive measure against the stress corrosion cracking (SCC) phenomenon in many boiling water reactors. However, it can be applied only during normal plant operation since hydrogen is usually injected into the feedwater and this system is in standby mode during start-up operations. It is estimated that the core internals are subjected to the strain rate that may cause susceptibility to SCC initiation during start-up. Therefore, it is beneficial to perform hydrogen injection during start-up as well in order to suppress SCC initiation.For this purpose, we installed an additional hydrogen injection system to be used during plant start-up at the Tokai-2 power station. This trial Hydrogen water chemistry During Start-up (HDS) system was applied following the 19th refueling and maintenance outage in December 2002. By comparing results obtained during this start-up with HDS to previous start-up data using normal water chemistry, we made the following observations. First, as the reactor water temperature increased from initial conditions up to 180°C via nuclear heating, dissolved oxygen and hydrogen peroxide concentrations decreased to levels lower than previously observed. Second, during subsequent nuclear heating, up to 250°C, the dissolved oxygen concentration did not exceed 1 ppb, and the electrochemical corrosion potential was maintained in a low range near -400 mV versus the standard hydrogen electrode.