Adoption of ACPS in Nuclear Reactor Analysis

Author:

Castagna Christian1,Cancila Daniela2,Cammi Antonio3

Affiliation:

1. The Unit of Nuclear Engineering, Ben-Gurion University of the Negev, Beer-Sheva, Israel

2. Université Paris Saclay, CEA LIST, Gif-sur-Yvettes, France

3. Politecnico di Milano, Department of Energy, CeSNEF (Enrico Fermi Center for Nuclear Studies), Milano, Italy

Abstract

Nuclear power plants are a paramount example of critical cyber-physical systems. Some of the current researches in nuclear reactor analysis concern the degree of acceptable uncertainty of the whole system. Some difficulties arise from weaving fields of different disciplines, such as computer science (e.g. embedded software and hardware), mechatronics (e.g. sensors and actuators) and physics (e.g. neutronics and thermal-hydraulics). To complicate the scenario further, each field demands different disciplines, competencies and different teams. In this short paper, we highlight the importance of the cross-fertilization of different disciplines in the nuclear reactor domain and we investigate emerging methods to control uncertainty in the nuclear reactor design.

Publisher

Association for Computing Machinery (ACM)

Subject

General Medicine

Reference21 articles.

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2. International Atomic Energy Agency , IAEA Safety Glossary . 2018 . International Atomic Energy Agency, IAEA Safety Glossary. 2018.

3. IEC , IEC 60880 Nuclear power plants -- Instrumentation and control systems important to safety -- Software aspects for computer-based systems performing category A functions ., 2006 . IEC, IEC 60880 Nuclear power plants -- Instrumentation and control systems important to safety -- Software aspects for computer-based systems performing category A functions., 2006.

4. IEC, IEC 61513. Nuclear power plants -- Instrumentation and control important to safety -- General requirements for systems , 2011 . IEC, IEC 61513. Nuclear power plants -- Instrumentation and control important to safety -- General requirements for systems, 2011.

5. Review on neutronic/thermal-hydraulic coupling simulation methods for nuclear reactor analysis

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