ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
2021 ANS Virtual Annual Meeting
June 14–16, 2021
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 Science and Engineering
Fusion Science and Technology
How the NRC modernized its digital I&C infrastructure and where it goes from here
The Nuclear Regulatory Commissiona first formally developed infrastructure for the review of digital instrumentation and control (I&C) systems in the 1990s. Although the current fleet of nuclear power plants in the United States was originally designed and constructed with analog systems, the U.S. nuclear industry has for more than 30 years been working to upgrade these older systems with modern digital equipment.
K. L. Davis, D. L. Knudson, J. L. Rempe, J. C. Crepeau, S. Solstad
Nuclear Technology | Volume 191 | Number 1 | July 2015 | Pages 92-105
Technical Note | Materials for Nuclear Systems | dx.doi.org/10.13182/NT14-60
Articles are hosted by Taylor and Francis Online.
New materials are being considered for fuel, cladding, and structures in next-generation and existing nuclear reactors. Such materials can undergo significant dimensional and physical changes during high-temperature irradiation. To accurately predict these changes, real-time data must be obtained under prototypic irradiation conditions for model development and validation. To provide these data, programs such as the Advanced Test Reactor (ATR) National Scientific Users Facility (NSUF) have funded researchers at the Idaho National Laboratory (INL) High Temperature Test Laboratory (HTTL) to develop several instrumented test rigs to obtain data in real time from specimens irradiated in well-controlled pressurized water reactor (PWR) coolant conditions in ATR. This technical note reports the status of INL efforts to develop and evaluate prototype test rigs that rely on linear variable differential transformers (LVDTs) in laboratory settings. Although similar LVDT-based test rigs have been deployed in lower-flux materials testing reactors (MTRs), this effort is unique because it relies on robust LVDTs that can withstand higher temperatures and higher fluxes than often found in other MTR irradiations. Specifically, the test rigs are designed for detecting changes in the length and diameter of specimens irradiated in ATR PWR loops. Once implemented, these test rigs will provide ATR users with unique capabilities that are sorely needed to obtain measurements, such as elongation caused by thermal expansion and/or creep loading, and diameter changes associated with fuel and cladding swelling, pellet-cladding interaction, and crud buildup.