Summary Review on the Application of Computational Fluid Dynamics in Nuclear Power Plant Design / IAEA, issuing body.

Format:

Book

Contributor:

IAEA, issuing body.

Series:

IAEA nuclear energy series ; Volume NR-T-1.20.

IAEA Nuclear Energy Series ; Volume NR-T-1.20

Language:

English

Subjects (All):

Computational fluid dynamics.

Nuclear power plants--Design and construction.

Nuclear power plants.

Physical Description:

1 online resource (119 pages)

Edition:

First edition.

Place of Publication:

Vienna, Austria : International Atomic Energy Agency, [2022]

Summary:

This publication by the International Atomic Energy Agency (IAEA) explores the application of computational fluid dynamics (CFD) in the design of nuclear power plants. It provides an overview of the role of CFD codes in optimizing water-cooled nuclear reactor designs, highlighting their use in technological development and safety analyses. The report compiles contributions from a coordinated research project involving 15 participants from 11 member states, aiming to establish a framework for the consistent application of CFD in nuclear engineering. It addresses the challenges and benefits of CFD applications, including best practice guidelines, experimental validation, and future developments in reactor types. The publication is intended for reactor designers, utilities, code developers, and research organizations involved in nuclear power plant design. Generated by AI.

Contents:

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.

Notes:

Description based on publisher supplied metadata and other sources.

Part of the metadata in this record was created by AI, based on the text of the resource.

Description based on print version record.

Includes bibliographical references.

Other Format:

Print version: IAEA Summary Review on the Application of Computational Fluid Dynamics in Nuclear Power Plant Design

ISBN:

9789201004215

OCLC:

1377815824