An Engineer’s Guide to Nuclear Reactor Core Materials
- 1st Edition - September 2, 2025
- Imprint: Academic Press
- Author: Malcolm Griffiths
- Language: English
- Paperback ISBN:9 7 8 - 0 - 4 4 3 - 3 0 1 0 4 - 9
- eBook ISBN:9 7 8 - 0 - 4 4 3 - 3 0 1 0 5 - 6
An Engineer’s Guide to Nuclear Reactor Core Materials details the impact of radiation damage on materials and offers tools for calculating atomic displacement and transmutatio… Read more
Purchase options
An Engineer’s Guide to Nuclear Reactor Core Materials details the impact of radiation damage on materials and offers tools for calculating atomic displacement and transmutation, specifically helium and hydrogen gas production using publicly available software from the IAEA website. Additionally, it explains the metallurgical properties of reactor components determined by microstructure and alloying elements, covering the effects of fabrication and subsequent irradiation. The book addresses radiation effects modeling, methods for determining microstructure parameters necessary for modeling, and the impact of radiation on materials such as creep, swelling, and hardening.
Rate theory formulations used in modeling radiation effects are explained, making it accessible for practical applications. It also simplifies tensors with examples and describes properties of common engineering alloys used in nuclear reactors, highlighting key features relevant to reactor operation. This reference is intended for nuclear engineers, reactor operators, academics, and students researching nuclear reactors.
Rate theory formulations used in modeling radiation effects are explained, making it accessible for practical applications. It also simplifies tensors with examples and describes properties of common engineering alloys used in nuclear reactors, highlighting key features relevant to reactor operation. This reference is intended for nuclear engineers, reactor operators, academics, and students researching nuclear reactors.
- Presents the effects of irradiation on core structural materials
- Suggests how to design new nuclear plants and how to select materials for refurbished units
- Discusses the mechanical properties of nuclear core materials and how they change during reactor operation
Nuclear engineers, reactor operations, and academics and students researching nuclear reactors
1. Physical Metallurgy
2. Radiation Damage Production and Transmutation
3. Microstructure
4. Mechanical properties
5. Fracture toughness and embrittlement
6. Dimensional Stability
7. Anisotropy and Tensors
8. Rate Theory
9. Microstructure Characterization
10. Everything a reactor engineer needs to know about Zr-alloys
11. Everything a reactor engineer needs to know about Ni-alloys
12. Everything a reactor engineer needs to know about Steels
13. Everything a reactor needs to know about Graphite
Appendix
A. CANDU Reactors
B. Materials Issues Life Management (Atucha Reactors)
C. Graphite-moderated reactors (AGR and RBMK
D. Light Water Reactors (PWR and BWR)
E. Gen IV Reactors
2. Radiation Damage Production and Transmutation
3. Microstructure
4. Mechanical properties
5. Fracture toughness and embrittlement
6. Dimensional Stability
7. Anisotropy and Tensors
8. Rate Theory
9. Microstructure Characterization
10. Everything a reactor engineer needs to know about Zr-alloys
11. Everything a reactor engineer needs to know about Ni-alloys
12. Everything a reactor engineer needs to know about Steels
13. Everything a reactor needs to know about Graphite
Appendix
A. CANDU Reactors
B. Materials Issues Life Management (Atucha Reactors)
C. Graphite-moderated reactors (AGR and RBMK
D. Light Water Reactors (PWR and BWR)
E. Gen IV Reactors
- Edition: 1
- Published: September 2, 2025
- Imprint: Academic Press
- Language: English
MG
Malcolm Griffiths
Dr. Malcolm Griffiths has worked on various aspects of materials performance in nuclear reactor cores during his 32 years with AECL. He was instrumental in developing strategies supporting CANDU refurbishment addressing improving pressure tube performance and the degradation of Inconel X-750 components in CANDU reactors. From 2003-2013, he was on the editorial advisory board for the Journal of Nuclear Materials and was an editor from 2013-2016. In 2007, he was recipient of the Kroll medal from the American Society for Testing and Materials for his pioneering work on microstructure evolution in zirconium alloys during irradiation.
While working at CRL, he was chair and project manager for the Candu Owners Group (COG) R&D program addressing Zr-2.5Nb pressure tube performance and the COG refurbishment joint project addressing Inconel X-750 spacer degradation. Since retiring in 2016, he is adjunct professor at Queens University and at Carleton University. He also consults through ANT International.
Affiliations and expertise
Adjunct Professor, Queens University, Carleton University, USA