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Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Reviewers needed for NRC research proposals
The deadline is fast approaching for submitting an application to become a technical reviewer for the Nuclear Regulatory Commission’s fiscal year 2025 research grant proposals.
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.
