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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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.
