Materials science and fuel technologies of uranium and plutonium mixed oxide /
edited by Masato Kato and Masahiko Machida.
- First edition.
- Boca Raton : Taylor & Francis, c2023.
- 182 p.:
Includes bibliographical references and index.
Experimental techniques -- Properties -- Theoretical and computational works on oxide nuclear-fuel materials -- Science-based model for MOX properties (Sci-M Pro.) -- Fuel performance analysis.
"Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide offers a deeper understanding of MOX properties for nuclear fuels that will be useful for performance evaluation. It also reviews fuel property simulation technology and an irradiation behavior model required for performance evaluation. Based on research findings, this book investigates various physical property data in order to develop MOX fuel for sodium-cooled fast reactors"--
English
9781003298205
2022015578
Mixed oxide fuels (Nuclear engineering)
Fuel--Testing--Simulation methods.
TK9360
333.7924/KAM
Includes bibliographical references and index.
Experimental techniques -- Properties -- Theoretical and computational works on oxide nuclear-fuel materials -- Science-based model for MOX properties (Sci-M Pro.) -- Fuel performance analysis.
"Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide offers a deeper understanding of MOX properties for nuclear fuels that will be useful for performance evaluation. It also reviews fuel property simulation technology and an irradiation behavior model required for performance evaluation. Based on research findings, this book investigates various physical property data in order to develop MOX fuel for sodium-cooled fast reactors"--
English
9781003298205
2022015578
Mixed oxide fuels (Nuclear engineering)
Fuel--Testing--Simulation methods.
TK9360
333.7924/KAM