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
Jan 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
February 2026
Nuclear Technology
January 2026
Fusion Science and Technology
November 2025
Latest News
Jeff Place on INPO’s strategy for industry growth
As executive vice president for industry strategy at the Institute of Nuclear Power Operations, Jeff Place leads INPO’s industry-facing work, engaging directly with chief nuclear officers.
Jason Chao, V. K. (Bindi) Chexal, William H. Layman, David A. Rautmann, Craig E. Peterson, Larry W. Cress
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 224-237
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33193
Articles are hosted by Taylor and Francis Online.
The RETRAN-02 and DYNODE-P thermal-hydraulic codes were compared against actual Prairie Island plant data from a steam generator tube break incident that occurred on October 2, 1979. The predictions from the code calculations compare well with actual plant behavior. The time of the break in the Prairie Island incident was found to be ∼260 s prior to scram with an initial break flow of 625 gal/min. Discharge coefficients are recommended for the calculations of critical flow from the break with extended Henry-Fauske and Moody critical flow models. In addition, a linear correlation was developed to predict the break flow with a given system depressurization rate for a Westinghouse two-loop plant.