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Record Nr. |
UNINA9910707412703321 |
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Autore |
Shih Chunkuan |
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Titolo |
Fuel rod behavior and uncertainty analysis by FRAPTRAN/TRACE/DAKOTA code in maanshan LBLOCA / / prepared by Chunkuan Shih [and five others] |
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Pubbl/distr/stampa |
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Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 2016 |
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Descrizione fisica |
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1 online resource (various pagings) : illustrations |
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Collana |
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International agreement report ; ; NUREG/IA-0471 |
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Soggetti |
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Nuclear fuel rods |
Nuclear reactor accidents - Analysis |
Pressurized water reactors - Loss of coolant - Analysis |
Nuclear power plants - Taiwan |
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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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"Institute of Nuclear Engineering and Science, National Tsing Hua University, Nuclear and New Energy Education and Research Foundation." |
"Department of Nuclear Safety, Taiwan Power Company." |
"K. Tien, NRC project manager." |
"Manuscript completed: March 2016; date published: August 2016." |
"Prepared as part of the agreement on research participation and technical exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)." |
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Nota di bibliografia |
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Includes bibliographical references. |
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