Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL
Joint Authors
Rais, A.
Siefman, D.
Girardin, G.
Hursin, M.
Pautz, A.
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2015, Issue 2015 (31 Dec. 2015), pp.1-9, 9 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2015-07-01
Country of Publication
Egypt
No. of Pages
9
Abstract EN
In order to analyze the steady state and transient behavior of the CROCUS reactor, several methods and models need to be developed in the areas of reactor physics, thermal-hydraulics, and multiphysics coupling.
The long-term objectives of this project are to work towards the development of a modern method for the safety analysis of research reactors and to update the Final Safety Analysis Report of the CROCUS reactor.
A first part of the paper deals with generation of a core simulator nuclear data library for the CROCUS reactor using the Serpent 2 Monte Carlo code and also with reactor core modeling using the PARCS code.
PARCS eigenvalue, radial power distribution, and control rod reactivity worth results were benchmarked against Serpent 2 full-core model results.
Using the Serpent 2 model as reference, PARCS eigenvalue predictions were within 240 pcm, radial power was within 3% in the central region of the core, and control rod reactivity worth was within 2%.
A second part reviews the current methodology used for the safety analysis of the CROCUS reactor and presents the envisioned approach for the multiphysics modeling of the reactor.
American Psychological Association (APA)
Rais, A.& Siefman, D.& Girardin, G.& Hursin, M.& Pautz, A.. 2015. Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL. Science and Technology of Nuclear Installations،Vol. 2015, no. 2015, pp.1-9.
https://search.emarefa.net/detail/BIM-1077823
Modern Language Association (MLA)
Rais, A.…[et al.]. Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL. Science and Technology of Nuclear Installations No. 2015 (2015), pp.1-9.
https://search.emarefa.net/detail/BIM-1077823
American Medical Association (AMA)
Rais, A.& Siefman, D.& Girardin, G.& Hursin, M.& Pautz, A.. Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL. Science and Technology of Nuclear Installations. 2015. Vol. 2015, no. 2015, pp.1-9.
https://search.emarefa.net/detail/BIM-1077823
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-1077823