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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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ANS standard updated for determining meteorological information at nuclear facilities
Following approval in October from the American National Standards Institute, ANSI/ANS-3.11-2024, Determining Meteorological Information at Nuclear Facilities, was published in late November. This standard provides criteria for gathering, assembling, processing, storing, and disseminating meteorological information at commercial nuclear power plants, U.S. Department of Energy/National Nuclear Security Administration nuclear facilities, and other national or international nuclear facilities.
Tsung-Kuang Yeh, Mei-Ya Wang
Nuclear Science and Engineering | Volume 173 | Number 2 | February 2013 | Pages 163-171
Technical Paper | doi.org/10.13182/NSE11-85
Articles are hosted by Taylor and Francis Online.
The coolant in a boiling water reactor (BWR) during a cold shutdown usually contains a relatively high level of dissolved oxygen from intrusion of atmospheric air. Accordingly, the structural materials in the primary coolant circuit (PCC) of a BWR could be exposed to a strongly oxidizing environment for a short period of time during a subsequent startup operation. Because there are limited measurable water chemistry data, a well-developed computer code DEMACE was used in the current study to investigate the variations in redox species concentration and in electrochemical corrosion potential (ECP) of components in the PCC of a domestic BWR during startup operations. Our analyses indicated that the dissolved hydrogen level in the reactor coolant at a low power level without steam generation in the core was lower than that at a power level with a minor amount of steam generated in the core. The dissolved oxygen concentrations in the reactor coolant were relatively high and were >500 ppb during startup operations at power levels >2.5%. In the meantime, the concentrations of hydrogen peroxide could be >500 ppb at the core outlet region during startup operations, which renders a strongly oxidizing coolant environment in the entire PCC. The ECPs of structural components in the PCC of the analyzed BWR generally followed the concentration trend of hydrogen peroxide. It was predicted that the coolant environment in a BWR during a plant startup could be highly oxidizing, and the structural components would therefore suffer from a more serious corrosion problem than under operations at the rated power level.