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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.
Abdelhamid Dokhane, Stefano Canepa, Hakim Ferroukhi
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 341-353
Technical Paper | Fission Reactors / Radiation Transport and Protection | doi.org/10.13182/NT13-A19423
Articles are hosted by Taylor and Francis Online.
For stability analyses of the Swiss operating boiling water reactors, the methodology employed and validated so far at the Paul Scherrer Institute (PSI) was based on the RAMONA-3 code with a hybrid upstream static lattice/core analysis approach using CASMO-4 and PRESTO-2. More recently, steps were undertaken toward a new methodology based on the SIMULATE-3K (S3K) code for the dynamical analyses combined with the CMSYS system, which relies on the CASMO/SIMULATE-3 suite of codes and was established at PSI to serve as framework for the development and validation of reference core models of all the Swiss reactors and operated cycles.This paper presents a first validation of the new methodology on the basis of a benchmark recently organized by a Swiss utility and including the participation of several international organizations with various codes/methods. Now in parallel, a transition from CASMO-4E (C4E) to CASMO-5M (C5M) as basis for the CMSYS core models was also recently initiated at PSI. Consequently, it was considered adequate to address the impact of this transition both for the steady-state core analyses as well as for the stability calculations and to achieve thereby an integral approach for the validation of the new S3K methodology. Therefore, a comparative assessment of C4 versus C5M is also presented in this paper, with particular emphasis on the void coefficients and their impact on the downstream stability analysis results.