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Assessment of RELAP5/MOD 2 against critical flow data from Marviken tests JIT 11 and CFT 21 / / prepared by Ö. Rosdahl, D. Caraher
| Assessment of RELAP5/MOD 2 against critical flow data from Marviken tests JIT 11 and CFT 21 / / prepared by Ö. Rosdahl, D. Caraher |
| Autore | Rosdahl Ö (Östen) |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , September 1986 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear pressure vessels
Light water reactors - Data processing Nuclear power plants - Thermodynamics Nuclear reactor kinetics |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Studsvik energiteknik AB |
| Record Nr. | UNINA-9910707414103321 |
Rosdahl Ö (Östen)
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , September 1986 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of RELAP5/MOD 2 against Marviken jet impingement test 11 level swell / / prepared by Ö. Rosdahl, D. Caraher
| Assessment of RELAP5/MOD 2 against Marviken jet impingement test 11 level swell / / prepared by Ö. Rosdahl, D. Caraher |
| Autore | Rosdahl Ö (Östen) |
| Pubbl/distr/stampa | Washington, D.C. : , : Office Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , September 1986 |
| Descrizione fisica | 1 online resource (v, 42 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear pressure vessels
Light water reactors - Data processing Nuclear power plants - Thermodynamics Nuclear reactor kinetics |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | ICAP assessment of RELAP5/MOD2 against Marviken jet impingement test 11 level swell |
| Record Nr. | UNINA-9910707419803321 |
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Rosdahl Ö (Östen)
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| Washington, D.C. : , : Office Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , September 1986 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of RELAP5/MOD 2, cycle 36, against FIX-II split break experiment no. 3027 / / prepared by J. Eriksson
| Assessment of RELAP5/MOD 2, cycle 36, against FIX-II split break experiment no. 3027 / / prepared by J. Eriksson |
| Autore | Eriksson J (John) |
| Pubbl/distr/stampa | Washington, D.C. : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , September 1986 |
| Descrizione fisica | 1 online resource (v, 43, 38 unnumbered pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Light water reactors - Data processing
Nuclear power plants - Thermodynamics Nuclear reactor kinetics |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707419703321 |
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Eriksson J (John)
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| Washington, D.C. : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , September 1986 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Consequential SGTR analysis for Westinghouse and combustion engineering plants with thermally treated alloy 600 and 690 steam generator tubes : draft report for comment / / prepared by S. Sancaktar [and four others]
| Consequential SGTR analysis for Westinghouse and combustion engineering plants with thermally treated alloy 600 and 690 steam generator tubes : draft report for comment / / prepared by S. Sancaktar [and four others] |
| Autore | Sancaktar S. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 2016 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Soggetto topico |
Steam-boilers
Tubes Combustion engineering Nuclear power plants - Thermodynamics Steel alloys |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Consequential SGTR analysis for Westinghouse and combustion engineering plants with thermally treated alloy 600 and 690 steam generator tubes |
| Record Nr. | UNINA-9910707654803321 |
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Sancaktar S.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 2016 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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ICAP assessment of RELAP5/MOD2, cycle 36.05 against LOFT small break experiment L3-7 / / prepared by Euy-Joon Lee, Bud-Dong Chung, Hho-Jung Kim
| ICAP assessment of RELAP5/MOD2, cycle 36.05 against LOFT small break experiment L3-7 / / prepared by Euy-Joon Lee, Bud-Dong Chung, Hho-Jung Kim |
| Autore | Lee Euy-Joon |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 1990 |
| Descrizione fisica | 1 online resource (v, 160 pages) : illustrations |
| Soggetto topico |
LOFT (Nuclear reactor safety test facility) - Experiments
Pressurized water reactors - Safety measures - Computer programs Nuclear power plants - Thermodynamics |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707628203321 |
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Lee Euy-Joon
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 1990 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Thermal mixing tests in a semiannular downcomer with interacting flows from cold legs / / prepared by H. Tuomisto, P. Mustonen
| Thermal mixing tests in a semiannular downcomer with interacting flows from cold legs / / prepared by H. Tuomisto, P. Mustonen |
| Autore | Tuomisto H (Harri) |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , October 1986 |
| Descrizione fisica | 1 online resouce (ix, 328 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Cooling - Testing
Nuclear power plants - Thermodynamics |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707419603321 |
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Tuomisto H (Harri)
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , October 1986 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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