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The human factor in licensing and operating the next generation of nuclear plants
As human factors specialists working at the intersection of human performance and nuclear operations, we are witnessing one of the nuclear sector’s most significant transitions in decades. The emergence of small modular reactors, microreactors, and other advanced designs is reshaping the industry’s landscape. Digital instrumentation and controls, passive safety systems, and increased automation are creating opportunities for greater safety margins and more flexible operation. These same features also fundamentally redefine what it means to “operate” a nuclear plant. Interactions among human roles, automation, and passive systems shape how people maintain awareness, exercise judgment, and intervene when necessary. These developments affect both operational realities and the regulatory foundations on which nuclear safety is built.
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.