Summary Review on the Application of Computational Fluid Dynamics in Nuclear Power Plant Design

Name: Summary Review on the Application of Computational Fluid Dynamics in Nuclear Power Plant Design
Brand: International Atomic Energy Agency
Price: 43.49 EUR
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IAEA(Autor*in)

International Atomic Energy Agency (Verlag)

Erschienen am 28. März 2022

90 Seiten

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978-92-0-100421-5 (ISBN)

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Inhalt

Intro
1. Introduction
1.1. Background
1.2. Objective
1.3. Scope
1.4. Structure
2. Roles of System Codes and Computational Fluid Dynamics in the Nuclear Power Plant Design Process
3. Activities involving Computational Fluid Dynamics in Support of Nuclear Power Plant Design
3.1. Reactor designers
3.1.1. Westinghouse
3.2. Utilities
3.2.1. Électricité de France
3.3. Code developers of computational fluid dynamics
3.3.1. Électricité de France
3.3.2. French Alternative Energies and Atomic Energy Commission
3.4. Research organizations
3.4.1. French Alternative Energies and Atomic Energy Commission
3.4.2. Canadian Nuclear Laboratories
3.4.3. Korea Atomic Energy Research Institute
3.4.4. Paul Scherrer Institute
3.4.5. Bhabha Atomic Research Centre
4. Status of Verification and Validation for the Use of Computational Fluid Dynamics in Nuclear Power Plant Design
4.1. Design applications
4.1.1. Électricité de France
4.1.2. Westinghouse
4.2. Validation gaps and issues involved
4.2.1. Électricité de France
4.2.2. Westinghouse
5. Future Use of Computational Fluid Dynamics for Selected Reactor Types
5.1. Supercritical water reactor
5.2. Water-water energetic reactor
5.2.1. Present limitations of computational fluid dynamics
5.2.2. Improvements needed
5.3. Sodium cooled fast reactors
5.3.1. Present limitations of computational fluid dynamics
5.3.2. Improvements needed
5.4. Pressurized water reactors
5.4.1. Present limitations of computational fluid dynamics
5.4.2. Improvements needed
6. Best practice Guidelines in the Use of Computational Fluid Dynamics for Nuclear Power Plant Design
6.1. Best practice guidelines for safety analyses
6.2. Specific examples
6.2.1. ROCOM test facility
6.2.2. HAWAC test facility
6.2.3. Vattenfall T-junction experiment
6.2.4. Hybiscus-2 test
6.2.5. Summary
7. Summary of Experimental Requirements for Producing Computational Fluid Dynamics Grade Data
7.1. General experimental requirements
7.2. Validation of two phase flow modelling for computational fluid dynamics
7.2.1. General requirements
7.2.2. Extra requirements for momentum transfer under two phase conditions
7.2.3. Requirements concerning the validation of turbulence models
8. User Qualification
8.1. General requirements for practitioners of computational fluid dynamics
8.2. Specific knowledge areas
8.2.1. Basic physics
8.2.2. Mathematics
8.2.3. Computer science and numerical analysis
8.3. Summary of training courses in computational fluid dynamics for reactor design
8.3.1. The HZDR multiphase flow workshop - short course and conference
8.3.2. IAEA training courses on computational fluid dynamics
8.3.3. Swiss Federal Institute of Technology short courses on multiphase flow
9. Uncertainty Quantification
9.1. Overview
9.2. Aspects of uncertainty quantification
9.2.1. Sources of uncertainty
9.2.2. Uncertainty propagation methods
9.2.3. Methods based on propagation of uncertainties
9.2.4. Accuracy extrapolation methods
9.2.5. Comparison of methods
9.3. The GEMIX benchmark
9.4. Conclusions
10. Gaps in Computational Fluid Dynamics Technology Applied to Nuclear Power Plant Design Issues
10.1. Verification and validation
10.2. Range of application of turbulence models
10.3. Stratification and buoyancy effects
10.4. Coupling system/computational fluid dynamics codes
10.4.1. Multiscale and multiphysics considerations
10.4.2. Isolating the computational fluid dynamics problem
10.4.3. Direct coupling of system codes with computational fluid dynamics codes
10.5. Coupling with other physics codes
10.5.1. Coupling of computational fluid dynamics code with neutronics codes
10.5.2. Coupling of computational fluid dynamics code with structural analysis codes
10.6. Computing power limitations
11. CONCLUSIONS
REFERENCES
ABBREVIATIONS
CONTRIBUTORS TO DRAFTING AND REVIEW
STRUCTURE OF THE IAEA NUCLEAR ENERGY SERIES

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