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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.
Gerald R. Mazetis, David D. Ebert
Nuclear Technology | Volume 67 | Number 3 | December 1984 | Pages 411-418
Technical Paper | Nuclear Safety | doi.org/10.13182/NT84-A33498
Articles are hosted by Taylor and Francis Online.
A method for nuclear power plant accident diagnostics using optimal control theory was investigated. A computer code, CAAD (Computer Assisted Accident Diagnostics), based on Pontryagin’s Principle, has been written and applied to single control malfunctions in nuclear power plants. Using a simplified systems model to represent power plant dynamics, the control theory in CAAD is expected to be suitable for expanding to more detailed systems applications. Results were obtained for a series of simulated plant transients that compare key state parameters to the control parameter output resulting from searches for the correct malfunction. A performance index is used as a convergence criterion upon which to define the degree of approach to the correct failure identification. The long-term goal of this methodology would be to expand to on-line computer application in reactor control rooms. Intended to be automatically initiated by a reactor accident, the malfunction search process would provide the operator with additional information to assist in identifying the most likely failure.