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Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
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
Federal court finds in favor of Diablo Canyon license review
A review from the Ninth Circuit Court of Appeals this week denied a challenge to the Diablo Canyon nuclear plant’s license renewal application extension granted by the federal government.
In late 2023, the Nuclear Regulatory Commission agreed to formally docket the California plant’s request to extend plant operations beyond the current license expiration dates of 2024 and 2025 for the two respective units.
Yacine Aounallah
Nuclear Technology | Volume 145 | Number 2 | February 2004 | Pages 163-176
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3467
Articles are hosted by Taylor and Francis Online.
CORETRAN-01 is the Electric Power Research Institute core analysis computer program that couples the neutronic code ARROTTA to the thermal-hydraulic code VIPRE-02 to achieve an integrated three-dimensional representation of the core for both steady-state and transient applications. The thermal-hydraulic module VIPRE-02, the two-fluid version of the one-fluid code VIPRE-01, has been the object of relatively few assessment studies, and the work presented seeks to reduce this lacuna. The priority has been given to the assessment of the void fraction prediction due to the importance of the void feedback on the core power generation. The assessment data are experimental void fractions obtained from X- and gamma-ray attenuation techniques applied at assembly-averaged as well as subchannel level for both steady-state and transient conditions. These experiments are part of the NUPEC (Japan) program where full-scale boiling water reactor (BWR) assemblies of different types, including assemblies with part-length rods, and pressurized water reactor subassemblies were tested at nominal reactor operating conditions, as well as for a range of flow rates and pressures. Generally, the code performance ranged from adequate to good, except for configurations exhibiting a strong gradient in power-to-flow ratio. Critical power predictions have also been assessed and code limitations identified, based on measurements on full-scale BWR 8 × 8 and high-burnup assemblies operated over a range of thermal-hydraulic conditions.