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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
Tsung-Kuang Yeh, Digby D. Macdonald
Nuclear Science and Engineering | Volume 123 | Number 2 | June 1996 | Pages 305-316
Technical Paper | doi.org/10.13182/NSE96-A24192
Articles are hosted by Taylor and Francis Online.
The DAMAGE-PREDICTOR computer code, which has the capability of simultaneously estimating the concentrations of radiolysis species, the electrochemical corrosion potential (ECP), and the crack growth rate (CGR) of a reference crack in sensitized Type 304 stainless steel, is used to evaluate the responses of the Dresden-2 and Duane Arnold boiling water reactors (BWRs) to hydrogen water chemistry (HWC) at different power levels. The HWC simulations for these two BWRs are carried out for feedwater hydrogen concentration ([H2]fw) ranging from 0.0 to 2.0 parts per million and for power levels at 100, 90, 80, and 70%. Variations in the oxygen, hydrogen peroxide, and hydrogen concentrations; ECP; and CGR for four specific areas (the side of the core shroud head, the base of the core shroud, the recirculation system outlet, and the bottom of the lower plenum) as a function of the feedwater hydrogen concentration and power level are analyzed. It is found that lower power levels alleviate the amount of hydrogen injected into the feedwater that is required to protect the reactor components from intergranular stress corrosion cracking. HWC is particularly effective in protecting the base of the core shroud and the recirculation system outlet but is only moderately effective in protecting the bottom of the lower plenum. On the other hand, the ECP and the CGR at the side of the core shroud head seem to be indifferent to both the operating power level and the feedwater hydrogen concentration.
