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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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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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Nuclear new build procurement considerations
It may seem counterintuitive, but the best time to enhance the ability to support operations and maintenance for a new plant is before construction starts. This is one of many lessons learned by the currently operating nuclear fleet. As construction and startup of many nuclear facilities was completed, it quickly became evident that the ability to efficiently support operations and maintenance was limited. Most of the information necessary to establish and manage procurement of spare and replacement items, maintenance, and configuration of the facilities was unavailable and had to be gathered on a case-by-case, “on-demand” basis. Absence of necessary information and the associated challenges resulted in the need for staff augmentation and multiyear-long projects to develop equipment bills of material and maintenance programs and to perform technical evaluations for the huge quantities of spare and replacement items being requested.
T. Ahn, H. Jung, P. Shukla, X. He
Nuclear Technology | Volume 182 | Number 1 | April 2013 | Pages 111-122
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT13-A15831
Articles are hosted by Taylor and Francis Online.
Crevice corrosion is the predominant mode of localized corrosion of Alloy 22 in concentrated chloride solutions at near-boiling temperatures. A literature review was performed to assess the electrochemical criteria for the long-term initiation of stable crevice corrosion of nickel-based or passive alloys, such as Alloy 22, in terms of likelihood, timing, and magnitude of potential damage due to crevice corrosion. The assessment in this study intends to predict the long-term performance of the waste package in nuclear waste management. Specifically, the areas of review included (a) environments (e.g., solution chemistry and electrochemical polarized condition) and crevice corrosion initiation criteria, (b) data and models for Alloy 22 crevice corrosion, and (c) induction times for crevice corrosion initiation. The assessment of the criteria for crevice corrosion initiation indicates that without externally applied current (i.e., at the open-circuit corrosion potential), initiation of crevice corrosion could be more difficult compared to the case when external current is applied. Without external current, crevice corrosion may not be initiated and sustained until the corrosion potential reaches the breakdown potential. Because the breakdown potential is typically more anodic than the repassivation potential, it is likely that the use of repassivation potential as the initiation criterion can overestimate a localized corrosion susceptibility. A short-term laboratory polarization test of Alloy 22 investigated whether any pits developed under the crevice were unstable for growth and if they could be stifled (i.e., suppressed). The long-term immersion tests of Alloy 22 exhibited a trend of continuous decrease of corrosion rate with time while the corrosion potential increased with time. An assessment of the theoretical models appeared to adequately scale induction time for crevice corrosion initiation to extrapolated long time periods.