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Record Nr. |
UNINA9910704812803321 |
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Autore |
Belaïd S. |
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Titolo |
Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE / / prepared by: S. Belaïd, J. Freixa, O. Zerkak |
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Pubbl/distr/stampa |
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Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 |
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Descrizione fisica |
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1 online resource (xiii, 29 pages) : color illustrations |
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Collana |
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International agreement report ; ; NUREG/IA-0432 |
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Soggetti |
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Pressurized water reactors - Testing |
Emergency core cooling systems - Testing |
Pressurized water reactors - Equipment and supplies - Effect of temperature on - Measurement |
Nuclear fuel claddings - Effect of temperature on - Measurement |
Nuclear power plants - Safety measures - Testing |
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Lingua di pubblicazione |
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Formato |
Materiale a stampa |
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Livello bibliografico |
Monografia |
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Note generali |
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Title from title screen (viewed Oct. 25, 2013). |
"September 2013." |
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Nota di bibliografia |
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Includes bibliographical references (page 29). |
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