Advanced numerical simulation and modelling for reactor safety - contribution from the CORTEX, HPMC, McSAFE and NURESAFE projects
- 1. Department of Physics, Division of Subatomic and Plasma Physics, Chalmers University of Technology, 412 96 Gothenburg (Sweden)
- 2. Institute for Neutron Physics and Reactor Technology - INR, Karlsruhe Institute of Technology - KIT, Hermann-vom-Helmholtz-Platz-1, 76344 Eggenstein-Leopoldshafen (Germany)
- 3. Commissariat a l'Energie Atomique et aux Energies Alternatives, Centre de Saclay, 91191 Gif-sur-Yvette Cedex (France)
Description
Predictive modelling capabilities have long represented one of the pillars of reactor safety. In this paper, an account of some projects funded by the European Commission within the seventh Framework Program (HPMC and NURESAFE projects) and Horizon 2020 Program (CORTEX and McSAFE) is given. Such projects aim at, among others, developing improved solution strategies for the modelling of neutronics, thermal-hydraulics, and/or thermo-mechanics during normal operation, reactor transients and/or situations involving stationary perturbations. Although the different projects have different focus areas, they all capitalize on the most recent advancements in deterministic and probabilistic neutron transport, as well as in DNS (direct numerical simulation), LES (large eddy simulation), CFD (computational fluid dynamics) and macroscopic thermal-hydraulics modelling. The goal of the simulation strategies is to model complex multi-physics and multi-scale phenomena specific to nuclear reactors. The use of machine learning combined with such advanced simulation tools is also demonstrated to be capable of providing useful information for the detection of anomalies during operation. (authors)
Availability note (English)
Available from doi: http://dx.doi.org/10.1051/epjn/2019006Additional details
Identifiers
- DOI
- 10.1051/epjn/2019006;
Publishing Information
- Journal Title
- EPJ Nuclear Sciences and Technologies
- Journal Volume
- 6
- Journal Page Range
- p. 42.1-42.14
- ISSN
- 2491-9292
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 52013796
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- COMPUTER CODES; COMPUTERIZED SIMULATION; COORDINATED RESEARCH PROGRAMS; EUROPEAN UNION; FLUID FLOW; INTERNATIONAL COOPERATION; NEUTRON TRANSPORT THEORY; REACTOR SAFETY; THERMODYNAMICS; VALIDATION
- Descriptors DEC
- COOPERATION; INTERNATIONAL ORGANIZATIONS; RESEARCH PROGRAMS; SAFETY; SIMULATION; TESTING; TRANSPORT THEORY
Optional Information
- Notes
- 28 refs.