Verification, Validation and Uncertainty Quantification of Multi-physics Modeling of Nuclear Reactors
Series: Woodhead Publishing Series in Energy;
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Product details:
- Publisher Woodhead Publishing
- Date of Publication 1 February 2023
- ISBN 9780128149546
- Binding Paperback
- No. of pages300 pages
- Size 229x152 mm
- Language English 0
Categories
Long description:
Verification, Validation and Uncertainty Quantification in Multi-physics Modeling of Nuclear Reactors is a key reference for those tasked with ensuring the credibility and reliability of engineering models and simulations for the nuclear industry and nuclear energy research. Sections discuss simulation challenges and revise key definitions, concepts and terminology. Chapters cover solution verification, the frontier discipline of multi-physics coupling verification, model validation and its applications to single and multi-scale models, and uncertainty quantification. This essential guide will greatly assist engineers, scientists, regulators and students in applying rigorous verification, validation and uncertainty quantification methodologies to the M&S tools used in the industry.
The book contains a strong focus on the verification and validation procedures required for the emerging multi-physics M&S tools that have great potential for use in the licensing of new reactors, as well as for power uprating and life extensions of operating reactors.
- Uniquely and crucially for nuclear engineers demonstrates the application of verification, validation and uncertainty methodologies to the modeling and simulation (M&S) of nuclear reactors
- Equips the reader to develop a rigorously defensible validation process irrespective of the particular M&S tool used
- Brings the audience up-to-speed on validation methods for traditional M&S tools
- Extends the discussion to the emerging area of validation of multi-physics and multi-scale nuclear reactor simulations
Table of Contents:
1. Introduction
2. Transport phenomena in nuclear reactors
3. Neutron transport: cell and assembly calculations
4. Neutron transport: core calculations
5. One-/two-phase flow transport and heat transfer
6. Neutronic/thermal-hydraulic coupling
7. Conclusion
