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Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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!
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Nuclear News 40 Under 40 discuss the future of nuclear
Seven members of the inaugural Nuclear News 40 Under 40 came together on March 4 to discuss the current state of nuclear energy and what the future might hold for science, industry, and the public in terms of nuclear development.
To hear more insights from this talented group of young professionals, watch the “40 Under 40 Roundtable: Perspectives from Nuclear’s Rising Stars” on the ANS website.
T. G. Broughton, N. G. Trikouros
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 342-357
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32779
Articles are hosted by Taylor and Francis Online.
The RETRAN code was developed in recognition of the need for utilities with a small analysis staff to be able to perform best-estimate analyses of operational transients. It provided General Public Utilities with a powerful tool for independent analysis of dynamic plant performance. Previously, all such best-estimate analyses were rarely performed, and only vendors, consultants, and large utilities had the required capability. The use of RETRAN by our own staff on our in-house computer has allowed us to establish our own schedules for a variety of analysis applications. In addition, the general nature of RETRAN allowed for the analysis of many different events with only minor changes to the model and for the modeling of both pressurized water reactor and boiling water reactor plants with the same code. To date, RETRAN has been successfully used to predict plant performance for the purposes of design optimization, short-term operational support, in-house support of licensing, and operator training activities. Plant procedures and postulated transient scenarios have been verified using RETRAN. Inferences have been made regarding the behavior of unrecorded plant parameters using the recorded parameters and iteratively varying the unknowns until a consistent simulation was obtained. This approach is presently being refined with the use of RETRAN control system models to preclude the need for iterative analyses. Our activities with RETRAN have given us confidence in the ability of the code to provide accurate thermal-hydraulic simulations, including simulations that require thermal-hydraulic and control system coupling. The importance of benchmarking against actual plant data as a means of providing confidence in the code and the particular plant models cannot be overemphasized. The control system models in RETRAN have been shown to provide a great deal of flexibility in displaying results in terms familiar to operations personnel and as a general means of problem solving. We anticipate an increased usage of RETRAN for operator training and procedure development. We also plan to conduct analyses of expected plant performance during different modes of operation such as startups and load changes. It is further anticipated that RETRAN will be used to provide prepredictions of plant performance during the Three Mile Island Unit 1 startup testing program. Future applications will include analyses in support of fuel reloads and plant modifications.