Materials science and fuel technologies of uranium and plutonium mixed oxide / edited by Masato Kato and Masahiko Machida.
Contributor(s): Kato, Masato (Researcher in nuclear energy) [editor.] | Machida, Masahiko [editor.].
Material type:
BookPublisher: Boca Raton : Taylor & Francis, c2023Edition: First edition.Description: 182 p.Content type: text Media type: computer Carrier type: online resourceISBN: 9781003298205.Subject(s): Mixed oxide fuels (Nuclear engineering) | Fuel -- Testing -- Simulation methodsAdditional physical formats: Print version:: Materials science and fuel technologies of uranium and plutonium mixed oxideDDC classification: 333.7924/KAM | Item type | Current location | Collection | Call number | Copy number | Status | Date due | Barcode |
|---|---|---|---|---|---|---|---|
| E-book | CUET CENTRAL LIBRARY Online Resources (See in online) | Non-fiction | 333.7924/KAM (Browse shelf) | 1 | Not for loan | E-192 |
Browsing CUET CENTRAL LIBRARY Shelves , Shelving location: Online Resources (See in online) , Collection code: Non-fiction Close shelf browser
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| 307.1216/GAS Smart, resilient and transition cities: | 332.63221/PAS The Sharpe ratio : | 333.7924/KAM Materials science and fuel technologies of uranium and plutonium mixed oxide / | 333.9170952/YAI Integrated coastal management in the japanese satoumi: | 363.61068/GAW The water sensitive city / | 363.7/BRE Environmental and pollution science / |
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"-- Provided by publisher.
NE
English
Description based on print version record and CIP data provided by publisher.
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