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Record Nr. |
UNINA9910706114003321 |
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Autore |
Vinogradov V. A. |
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Titolo |
Analyses of KS test data on the heated rod bundle temperature behavior in RBMK-1500 core model under stop and recovery flow using RELAP5/MOD3.2 and RELAP5/MOD3.2.2 GAMMA / / prepared by V.A. Vinogradov, A.Y. Balykin |
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Pubbl/distr/stampa |
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Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 2001 |
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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-0202 |
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Soggetti |
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Pressurized water reactors - Loss of coolant - Computer simulation |
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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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"Nuclear Reactor Institute, Russian Research Center, Kurchatov Institute." |
"April 2001." |
"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Code Application and Maintenance Program (CAMP)." |
"Sponsoring organization: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Bibliographic data sheet. |
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Nota di bibliografia |
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Includes bibliographical references (page 28). |
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