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
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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!
Latest Magazine Issues
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
November 2025
Nuclear Technology
October 2025
Fusion Science and Technology
Latest News
The current status of heat pipe R&D
Idaho National Laboratory under the Department of Energy–sponsored Microreactor Program recently conducted a comprehensive phenomena identification and ranking table (PIRT) exercise aimed at advancing heat pipe technology for microreactor applications.
Z. T. Mendoza, C. A. Stevens, R. L. Ritzman
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 155-162
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Nuclear Safety | doi.org/10.13182/NT81-A32620
Articles are hosted by Taylor and Francis Online.
Methodology often used to estimate the consequences of postulated nuclear reactor accidents was applied in an analysis of the SL-1 reactor accident, which occurred in January 1961. The work focused on use of the CORRAL and CRAC computer codes to predict radionuclide leakage from the accident and resulting downwind environmental contamination levels. Results were compared with findings developed from actual post-accident environmental sampling and analysis. The comparison indicated that the predictive capabilities of the two reactor accident consequence codes can be quite dependent on the input specifications for the analysis. In particular, the results show that the amount and the state of the initial source term is of considerable importance in determining the magnitude of the environmental contamination.