Analysis of the RELAP5/MOD3.2.2 beta critical flow models and assessment against critical flow data from the Marviken tests / / prepared by C. Queral, J. Mulas, C.G. de la Rua |
Autore | Queral César |
Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 2000 |
Descrizione fisica | 1 online resource (xx, 74 pages) : illustrations |
Collana | International agreement report |
Soggetto topico | Nuclear reactors - Cooling - Computer simulation |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910706149303321 |
Queral César | ||
Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 2000 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Assessment of RELAP5/MOD3.2 with the LSTF experiment simulating a loss of residual heat removal event during mid-loop operation / / prepared by K.W. Seul [and three others] |
Autore | Seul K. W. |
Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 1998 |
Descrizione fisica | 1 online resource (various pagings) : illustrations |
Collana | International agreement report |
Soggetto topico |
Nuclear reactors - Cooling - Computer simulation
Nuclear reactor accidents - Computer simulation |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910705827603321 |
Seul K. W. | ||
Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 1998 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Assessment study on the PMK-2 total loss of feedwater experiment using RELAP5 code / / prepared by J. Bánáti |
Autore | Bánáti J (Jozsef) |
Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , March 2001 |
Descrizione fisica | 1 online resource (ix, 24 pages) : illustrations |
Collana | International agreement report |
Soggetto topico |
Nuclear reactor accidents - Computer simulation
Nuclear reactors - Cooling - Computer simulation Nuclear reactors - Safety measures |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Altri titoli varianti | Assessment study on the PMK 2 total loss of feedwater experiment using RELAP5 code |
Record Nr. | UNINA-9910706114403321 |
Bánáti J (Jozsef) | ||
Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , March 2001 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Improvement of RELAP5/MOD3.3 reflood model based on the assessments against FLECHT-SEASET tests [[electronic resource] /] / prepared by Tong-Soo Choi ... [and others] |
Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2011] |
Descrizione fisica | 1 online resource (xiii, 137 pages) : color illustrations |
Collana | International agreement report |
Soggetto topico |
Light water reactors - Data processing
Steam-boilers - Evaluation Pressurized water reactors - Loss of coolant - Safety measures Nuclear reactors - Cooling - Computer simulation |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910700591903321 |
Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2011] | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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