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
Apr 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
May 2026
Nuclear Technology
March 2026
Fusion Science and Technology
Latest News
Access anywhere, anytime: Nuclear power, Ice Camp, and Rickover’s enduring standard of excellence
Admiral William Houston
As U.S. Navy submarines surface through Arctic ice during Ice Camp 2026, they demonstrate more than operational proficiency in one of the harshest environments on Earth. They reaffirm a technological truth first proven in August 1958, when the USS Nautilus completed its submerged transit of the North Pole: nuclear power enables access anywhere, anytime.
The Arctic is unforgiving, with vast distances, extreme cold, shifting ice, and no logistical infrastructure. Conventional propulsion is constrained by fuel, air, and endurance. Nuclear propulsion removes those constraints. Only a nuclear-powered submarine can operate anywhere in the world’s oceans, including under the polar ice, undetected and at maximum capability for extended periods. Nuclear power provides sustained high speed and the endurance to reposition across the globe without refueling.
Hakim Ferroukhi, Paul Coddington
Nuclear Technology | Volume 142 | Number 1 | April 2003 | Pages 19-34
Technical Paper | RETRAN | doi.org/10.13182/NT03-A3371
Articles are hosted by Taylor and Francis Online.
A code environment based on the CORETRAN and RETRAN-3D codes for the three-dimensional (3-D) kinetic analysis of transients in Swiss light water reactors is currently being developed and implemented within the STARS project at the Paul Scherrer Institute (PSI). As a first step in the application of these codes, an assessment of both codes for the analysis of reactivity-initiated transients in pressurized water reactors (PWRs) was performed. For that purpose, the Nuclear Energy Agency benchmark exercises, consisting of rod ejection and uncontrolled rod bank withdrawal transients, were selected. These analyses showed that very satisfactory results could be obtained with both CORETRAN and RETRAN-3D. In this paper, a summary of the PWR results, along with an emphasis of important modeling options that were identified during that work, is presented. As a second step, it was considered important to assess both codes for boiling water reactor (BWR) reactivity transients. Therefore, in addition, the analysis of a hypothetical beyond-design-basis rod drop accident for a Swiss BWR core at end of cycle is presented in this paper. This transient, which was previously analyzed with another 3-D code at PSI, shows that also for BWRs, both codes give satisfactory results.