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 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Nov 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
Latest News
Education and training to support Canadian nuclear workforce development
Along with several other nations, Canada has committed to net-zero emissions by 2050. Part of this plan is tripling nuclear generating capacity. As of 2025, the country has four operating nuclear generating stations with a total of 17 reactors, 16 of which are in the province of Ontario. The Independent Electricity System Operator has recommended that an additional 17,800 MWe of nuclear power be added to Ontario’s grid.
Glenn J. Neises, Terry J. Garrett
Nuclear Technology | Volume 93 | Number 1 | January 1991 | Pages 22-35
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A34515
Articles are hosted by Taylor and Francis Online.
A steam line break transient is analyzed for the Wolf Creek Generating Station using RETRAN02/MOD3. The RETRAN analysis results and the modeling approaches used for the steam line break transient are described. The results of this analysis are compared with the results of the Wolf Creek Updated Safety Analysis Report (USAR). The steam line break results presented in the USAR comparison include mixing between the affected and unaffected loops in the reactor vessel, boron tracking in the reactor coolant system, and sensitivity studies of various parameters.