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Modification of USNRC's FRAP-T6 fuel rod transient code for high burnup VVER fuel / / prepared by A. Shestopalov [and four others]
| Modification of USNRC's FRAP-T6 fuel rod transient code for high burnup VVER fuel / / prepared by A. Shestopalov [and four others] |
| Autore | Shestopalov A. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 1999 |
| Descrizione fisica | 1 online resource (57, A-48, B-2 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear fuel rods - Thermal properties - Computer programs
Nuclear fuel claddings - Thermal properties - Computer programs Nuclear reactor accidents - Computer simulation |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti |
Modification of USNRC's FRAP T6 fuel rod transient code for high burnup VVER fuel
Modification of U.S. NRC's FRAP-T6 fuel rod transient code for high burnup VVER fuel Modification of United States Nuclear Regulatory Commission's FRAP-T6 fuel rod transient code for high burnup VVER fuel |
| Record Nr. | UNINA-9910705837003321 |
Shestopalov A.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 1999 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Post-test calculations on steam cool-down test QUENCH-04 with RELAP5, SCDAP/RELAP5, and TRACE [[electronic resource] /] / prepared by Ch. Homann, W. Hering
| Post-test calculations on steam cool-down test QUENCH-04 with RELAP5, SCDAP/RELAP5, and TRACE [[electronic resource] /] / prepared by Ch. Homann, W. Hering |
| Autore | Homann Ch |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2011] |
| Descrizione fisica | 1 online resource (xiii, 51 pages) : illustrations |
| Altri autori (Persone) | HeringW |
| Collana | International agreement report |
| Soggetto topico |
Nuclear power plants - Safety measures - Computer simulation
Nuclear reactor accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910703398003321 |
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Homann Ch
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2011] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Post-test thermal-hydraulic analysis of PKL tests F1.1 and F1.2 / / prepared by J. Freixa [and three others] ; prepared for Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
| Post-test thermal-hydraulic analysis of PKL tests F1.1 and F1.2 / / prepared by J. Freixa [and three others] ; prepared for Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission |
| Autore | Freixa J. |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , October 2014 |
| Descrizione fisica | 1 online resource (73 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear power plants - Accidents - Computer simulation
Nuclear power plants - Computer programs - Testing Pressurized water reactors - Loss of coolant - Computer simulation Nuclear reactor accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910703560503321 |
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Freixa J.
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , October 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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RELAP5/MOD3 assessment using the semiscale 50% feed line break test S-FS-11 / / prepared by E.J. Lee, B.D. Chung, H. J. Kim
| RELAP5/MOD3 assessment using the semiscale 50% feed line break test S-FS-11 / / prepared by E.J. Lee, B.D. Chung, H. J. Kim |
| Autore | Lee E. J. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 1993 |
| Descrizione fisica | 1 online resource (xv, 54, 102, 6 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico | Nuclear reactor accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707852203321 |
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Lee E. J.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 1993 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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RELAP5/MOD3 subcooled boiling model assessment / / prepared by A.S. Devkin and A.S. Podosenov
| RELAP5/MOD3 subcooled boiling model assessment / / prepared by A.S. Devkin and A.S. Podosenov |
| Autore | Devkin A. S. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 1998 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Ebullition - Computer simulation
Heat - Transmission - Computer simulation Nuclear reactor accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910708489703321 |
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Devkin A. S.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 1998 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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RELAP5/MOD3.3 assessment by comparison with PKL III G3.1 experiment (small break in the main steam line) / / prepared by A. Zaruba, K. Krezeminski, A. Benkert
| RELAP5/MOD3.3 assessment by comparison with PKL III G3.1 experiment (small break in the main steam line) / / prepared by A. Zaruba, K. Krezeminski, A. Benkert |
| Autore | Zaruba A. |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014 |
| Descrizione fisica | 1 online resource (43 unnumbered pages) : illustrations |
| Collana | NUREG/IA |
| Soggetto topico |
Nuclear reactor accidents - Evaluation
Nuclear reactor accidents - Computer simulation Nuclear power plants - Accidents |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | RELAP5/MOD3.3 assessment by comparison with PKL III G3.1 experiment |
| Record Nr. | UNINA-9910702556103321 |
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Zaruba A.
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Result of BETHSY test 9.1.b using RELAP5/MOD3 / / prepared by S. Petelin [and four others]
| Result of BETHSY test 9.1.b using RELAP5/MOD3 / / prepared by S. Petelin [and four others] |
| Autore | Petelin S. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 1998 |
| Descrizione fisica | 1 online resource (80 unnumbered pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant - Computer simulation
Nuclear reactor accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707641803321 |
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Petelin S.
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| 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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Thermal hydraulic and fuel rod mechanical combination analysis of Kuosheng Nuclear Power Plant with RELAP5 MOD3.3/FRAPTRAN/Python in SNAP interface / / prepared by Jong-Rong Wang [and five others]
| Thermal hydraulic and fuel rod mechanical combination analysis of Kuosheng Nuclear Power Plant with RELAP5 MOD3.3/FRAPTRAN/Python in SNAP interface / / prepared by Jong-Rong Wang [and five others] |
| Autore | Wang Jong-Rong |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , November 2016 |
| Descrizione fisica | 1 online resource (xv, 45 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear reactor accidents - Computer simulation
Nuclear fuel rods - Testing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910708659903321 |
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Wang Jong-Rong
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| Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , November 2016 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Uncertainty analysis for Maanshan LBLOCA by TRACE and DAKOTA / / prepared by Jong-Rong Wang [and three others]
| Uncertainty analysis for Maanshan LBLOCA by TRACE and DAKOTA / / prepared by Jong-Rong Wang [and three others] |
| Autore | Wang Jong-Rong |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014 |
| Descrizione fisica | 1 online resource (53 unnumbered pages) : color illustrations |
| Collana | NUREG/IA |
| Soggetto topico |
Nuclear reactor accidents - Analysis
Nuclear reactor accidents - Computer simulation Pressurized water reactors - Loss of coolant - Analysis |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910702555803321 |
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Wang Jong-Rong
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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