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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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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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Latest News
Japanese researchers test detection devices at West Valley
Two research scientists from Japan’s Kyoto University and Kochi University of Technology visited the West Valley Demonstration Project in western New York state earlier this fall to test their novel radiation detectors, the Department of Energy’s Office of Environmental Management announced on November 19.
Hossein Zayermohammadi Rishehri, Majid Zaidabadi Nejad
Nuclear Technology | Volume 209 | Number 2 | February 2023 | Pages 193-213
Technical Paper | doi.org/10.1080/00295450.2022.2120319
Articles are hosted by Taylor and Francis Online.
Small modular reactors (SMRs) can be a significant option for developing countries with low energy demand. Due to the lack of sufficient experience in the field of SMRs, extensive research should be done on SMRs to improve the performance of these systems. Using dual surface-cooled fuel (DSCF) is one of the methods that can increase the performance of SMRs. In this study, for the first time the core of a NuScale reactor (as a SMR) is designed based on DSCF without any change in core dimensions by analyzing neutronic, thermal-hydraulic, and natural circulation parameters. In addition, according to the departure from nucleate boiling ratio, the uprate of the thermal power in a reactor using DSCF is investigated. For this purpose, typical solid fuels as well as DSCFs under clean-cold and full-power conditions are primarily modeled for the four different lattices that maintain the same assembly dimensions, mass, and enrichment fuels as the original fuel assembly. The effective multiplication factor, and power peaking factor, as important neutronic parameters, are calculated. Then the departure from nucleate boiling, pressure drop, velocity, and temperature distribution calculations, as important thermal-hydraulic and natural circulation parameters, are accomplished via a computational fluid dynamics code. The best core configuration of DSCF for the NuScale core is determined based on comparing the neutronic, thermal-hydraulic, and natural circulation parameters of various lattices and typical solid fuels. Regarding the final result, a DSCF assembly configuration, called a 12 × 12 assembly, is suggested.