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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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!
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RP3C Community of Practice’s fifth anniversary
In February, the Community of Practice (CoP) webinar series, hosted by the American Nuclear Society Standards Board’s Risk-informed, Performance-based Principles and Policies Committee (RP3C), celebrated its fifth anniversary. Like so many online events, these CoPs brought people together at a time when interacting with others became challenging in early 2020. Since the kickoff CoP, which highlighted the impact that systems engineering has on the design of NuScale’s small modular reactor, the last Friday of most months has featured a new speaker leading a discussion on the use of risk-informed, performance-based (RIPB) thinking in the nuclear industry. Providing a venue to convene for people within ANS and those who found their way online by another route, CoPs are an opportunity for the community to receive answers to their burning questions about the subject at hand. With 50–100 active online participants most months, the conversation is always lively, and knowledge flows freely.
L. Castelnau, T. Desmas, A. M. Lapicore, P. Mainy
Nuclear Technology | Volume 58 | Number 2 | August 1982 | Pages 171-183
Materials Performance in Nuclear Steam Generator | Material | doi.org/10.13182/NT82-A32929
Articles are hosted by Taylor and Francis Online.
Mandatory safety-related design requirements for this type of equipment include essentially the absolute leak-tightness of the heat exchange surfaces separating sodium from water and the prevention of violent sodium-water reactions. After briefly recalling the various situations likely to give rise to leaks, their evolution (self-wastage), and consequences (wastage and secondary ruptures), the precautions taken during steam generator (SG) designing, manufacturing, and operating phases to minimize leak hazards and satisfy the mechanical design basis requirements adopted for secondary loop components are analyzed. The in-service monitoring systems provided (hydrogen detection, acoustic detection) and the means devised to keep leak consequence within acceptable limits (rupture disks) are described. The automatic or operator-controlled actions initiated by signals from these systems are reviewed (reactor shutdown, SG isolation pressure relief, cooling and inertization of sodium or water-steam circuits). Plant overhaul procedures, servicing operations on the SG itself (whipping tube localization, damage assessment on adjoining tubes by insertion of an eddy-current probe, removal of damaged tubes) and on the secondary loop after detection and prior to restartup are presented. For each device and situation mentioned, a comparison is drawn, underlining the fundamental differences existing in the different types of SGs and tube materials.