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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Deep Space: The new frontier of radiation controls
In commercial nuclear power, there has always been a deliberate tension between the regulator and the utility owner. The regulator fundamentally exists to protect the worker, and the utility, to make a profit. It is a win-win balance.
From the U.S. nuclear industry has emerged a brilliantly successful occupational nuclear safety record—largely the result of an ALARA (as low as reasonably achievable) process that has driven exposure rates down to what only a decade ago would have been considered unthinkable. In the U.S. nuclear industry, the system has accomplished an excellent, nearly seamless process that succeeds to the benefit of both employee and utility owner.
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.
