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Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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
The progress so far: An update on the Reactor Pilot Program
It has been about three months since the Department of Energy named 10 companies for its new Reactor Pilot Program, which maps out how the DOE would meet the goal announced by executive order in May of having three reactors achieve criticality by July 4, 2026.
Huihua Yang, Qiyun Cheng, Ling Zou, Rui Hu, Wei Ji
Nuclear Technology | Volume 211 | Number 9 | September 2025 | Pages 1960-1985
Research Article | doi.org/10.1080/00295450.2024.2421678
Articles are hosted by Taylor and Francis Online.
With the increased interest in the design and deployment of advanced reactor systems, a desire for simulation tools supporting system analyses of reactor operation and safety is rising. Molten salt reactors (MSRs), one of the advanced reactor systems, utilize liquid-fused salt fuel as both coolant and fuel. During operation, MSRs generate insoluble fission products, including noble metals and gases. The buildup of these species in the fuel salt presents safety concerns, as they may deposit on surfaces of critical components and produce excessive decay heat, causing the failure of system components. The timely removal of these noble metals and gases would ensure the safe operation of the reactor system. The dynamic nature of salt fuel systems, involving the generation, decay, deposition, and extraction of noble metals and gases, calls for robust species transport models to facilitate system analysis and monitoring and the design of efficient species removal components. This paper concentrates on the development of a computational framework for species transport consisting of multiphase transport model formulation, mass transfer between phases, numerical implementation in the MOOSE environment, verification through the method of manufacture solutions, and validation against experimental data from the Molten Salt Reactor Experiment. Integrating this framework into the System Analysis Module (SAM) code further enhances SAM’s capabilities for advanced reactor analysis in the future.