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 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Jun 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
July 2026
Nuclear Technology
June 2026
Fusion Science and Technology
May 2026
Latest News
MARVEL team shares lessons learned through microreactor development
On June 1 at the American Nuclear Society’s Annual Conference in Denver, Colo., a team from Idaho National Laboratory presented a session titled “Lessons Learned from MARVEL Reactor Fabrication.” The presentation highlighted challenges that arose as they moved from design to manufacturing and assembly, with a focus on reactor part fabrication, Stirling engine implementation, and reactivity control system development.
Edward A. Boucheron, John E. Kelly
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 1050-1057
Late Paper | TMI-2: Decontamination and Waste Management / Nuclear Safety | doi.org/10.13182/NT89-A27696
Articles are hosted by Taylor and Francis Online.
The MELCOR computer code has been used to analyze the first 174 min of the Three Mile Island Unit 2 (TMI-2) accident. MELCOR is being developed at Sandia National Laboratories for the U.S Nuclear Regulatory Commission for the purpose of analyzing severe accidents in nuclear power plants. Comparison of the code predictions to the available data shows that MELCOR is capable of modeling the key events of the TMI-2 accident, and reasonable agreement with the available data is obtained. In particular, the core degradation and hydrogen generation models agree with best-estimate information available for this phase of the accident. While the code uses simplified modeling, all important characteristics of the reactor system and the accident phenomena could be modeled. This exercise demonstrates that MELCOR is applicable to severe accident analysis.