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Analysis of semiscale test S-LH-1 using RELAP5/MOD2 / / prepared by P.C. Hall, D.R. Bull
| Analysis of semiscale test S-LH-1 using RELAP5/MOD2 / / prepared by P.C. Hall, D.R. Bull |
| Autore | Hall P. C (Peter C.) |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1992 |
| Descrizione fisica | 1 online resource (v, 32 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Testing
Emergency core cooling systems - Testing |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Analysis of semiscale test S LH 1 using RELAP5/MOD2 |
| Record Nr. | UNINA-9910707780003321 |
Hall P. C (Peter C.)
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1992 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE / / prepared by: S. Belaïd, J. Freixa, O. Zerkak
| Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE / / prepared by: S. Belaïd, J. Freixa, O. Zerkak |
| Autore | Belaïd S. |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 |
| Descrizione fisica | 1 online resource (xiii, 29 pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
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 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Analysis of the test Organisation for Economic Co-operation and Development-Primary Coolant Loop Test Facility G7.1 with the thermal-hydraulic system code TRACE |
| Record Nr. | UNINA-9910704812803321 |
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Belaïd S.
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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RELAP/MOD3 analysis of BETHSY test 6.9c : loss of RHRS: SG manway open / / prepared by G.R. Kimber, M.A. George
| RELAP/MOD3 analysis of BETHSY test 6.9c : loss of RHRS: SG manway open / / prepared by G.R. Kimber, M.A. George |
| Autore | Kimber G. R. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 2000 |
| Descrizione fisica | 1 online resource (vii, 49 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Testing
Emergency core cooling systems - Testing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | RELAP/MOD3 analysis of BETHSY test 6.9c |
| Record Nr. | UNINA-9910706149203321 |
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Kimber G. R.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 2000 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Soggetto topico
-
Emergency core cooling systems - Testing
(3)
- Pressurized water reactors - Testing (3)
- Nuclear fuel claddings - Effect of temperature on - Measurement (1)
- Nuclear power plants - Safety measures - Testing (1)
- Pressurized water reactors - Equipment and supplies - Effect of temperature on - Measurement (1)