ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Feb 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
January 2026
Latest News
ANS 2026 election is open
The 2026 American Nuclear Society election is now open. Members can vote for the Society’s next vice president/president-elect as well as six board members (five U.S. directors and one non-U.S. director). Completed ballots must be submitted by 12:00 p.m. (CDT) on Wednesday, April 1, 2026.
All ANS members have been emailed a unique access key from third-party election vendor ElectionBuddy. Each member can use their access key to vote once, and each vote will remain anonymous. Visit secure.electionbuddy.com/ballot to vote.
Eric Cervi, Sébastien Baudier, Ling Zou, Rui Hu
Nuclear Technology | Volume 211 | Number 9 | September 2025 | Pages 2045-2069
Research Article | doi.org/10.1080/00295450.2024.2338506
Articles are hosted by Taylor and Francis Online.
Software verification and validation constitute crucial phases in the development of simulation computer codes, particularly in the context of nuclear reactor safety analysis codes, where stringent safety requirements govern the development and deployment of nuclear technologies. This paper focuses on numerical verification study of the System Analysis Module (SAM) computer code, currently under development at Argonne National Laboratory. Specifically, we employed the Method of Manufactured Solutions (MMS) and proposed a verification technique tailored to the multiphysics simulation of molten salt reactors (MSRs). This research accomplished three main objectives. First, we have addressed key challenges associated with applying the MMS to MSR systems, arising from (1) the complex multiphysics coupling inherent in this problem and (2) the necessity to model the entire coolant loop for describing the drift of delayed neutron precursors outside the reactor core. The paper provides recommendations and guidelines to overcome these challenges, enabling the successful application of the MMS for simulating MSRs. Second, we have presented a comprehensive set of verification examples, serving as an exhaustive benchmark for code verification within the nuclear community. Third, we have established a robust verification of the SAM code’s capability to model MSR systems.