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2D/3D Program work summary report / / edited by P.S. Damerell, J. W. Simons
| 2D/3D Program work summary report / / edited by P.S. Damerell, J. W. Simons |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 1993 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Collana |
GRS
International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant
Pressurized water reactors - Safety measures |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707866403321 |
| 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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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
| 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 |
| Autore | Vinogradov V. A. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 2001 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Collana | International agreement report |
| Soggetto topico | Pressurized water reactors - Loss of coolant - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910706114003321 |
Vinogradov V. A.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 2001 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Analysis of inadvertent pressurizer spray valve opening real transient with RELAP5/MOD3.2 / / prepared by J. Blanco [and four others]
| Analysis of inadvertent pressurizer spray valve opening real transient with RELAP5/MOD3.2 / / prepared by J. Blanco [and four others] |
| Autore | Blanco J. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , January 2001 |
| Descrizione fisica | 1 online resource (xiii, 63 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico | Pressurized water reactors - Accidents - Spain - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910706146403321 |
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Blanco J.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , January 2001 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Analysis of KS-1 experimental data on the behavior of the heated rod temperatures in the partially uncovered VVER core model using RELAP5/MOD3.2 / / prepared by V.A. Vinogradov, A.Y. Balykin
| Analysis of KS-1 experimental data on the behavior of the heated rod temperatures in the partially uncovered VVER core model using RELAP5/MOD3.2 / / prepared by V.A. Vinogradov, A.Y. Balykin |
| Autore | Vinogradov V. A. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , November 1999 |
| Descrizione fisica | 1 online resource (110 unnumbered pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear fuel rods - Thermal properties - Computer simulation
Nuclear fuels - Analysis - Computer simulation Nuclear fuel elements - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707110003321 |
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Vinogradov V. A.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , November 1999 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Analysis of LOBI test BLO2 (three percent cold leg break) with RELAP5 code / / prepared by A.H. Scriven
| Analysis of LOBI test BLO2 (three percent cold leg break) with RELAP5 code / / prepared by A.H. Scriven |
| Autore | Scriven A. H. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1992 |
| Descrizione fisica | 1 online resource (iii, 64 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear reactors - Testing - Data processing
Nuclear reactor kinetics - Data processing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Analysis of LOBI test BLO2 |
| Record Nr. | UNINA-9910707626503321 |
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Scriven A. H.
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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 LOFT test L5-1 using RELAP5/MOD2 / / prepared by S. Cooper
| Analysis of LOFT test L5-1 using RELAP5/MOD2 / / prepared by S. Cooper |
| Autore | Cooper S. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 1993 |
| Descrizione fisica | 1 online resource (v, 34 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Great Britain - Loss of coolant - Experiments
LOFT (Nuclear reactor safety test facility) |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Analysis of LOFT test L5 1 using RELAP5/MOD2 |
| Record Nr. | UNINA-9910707877403321 |
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Cooper S.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 1993 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Analysis of PANDA experiments P3 and P6 using RELAP5/MOD3.2 / / prepared by L. Batet, F. Reventós
| Analysis of PANDA experiments P3 and P6 using RELAP5/MOD3.2 / / prepared by L. Batet, F. Reventós |
| Autore | Batet L. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , January 2001 |
| Descrizione fisica | 1 online resource (xi, 16 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico | Water cooled reactors - Loss of coolant - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910706146203321 |
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Batet L.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , January 2001 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Analysis of pin-by-pin effects for LWR rod ejection accident / / prepared by A. Avvakumov, V. Malofeev, V. Sidorov
| Analysis of pin-by-pin effects for LWR rod ejection accident / / prepared by A. Avvakumov, V. Malofeev, V. Sidorov |
| Autore | Avvakumov A. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , March 2000 |
| Descrizione fisica | 1 online resource (xi, 77 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Light water reactors - Accidents - Computer simulation
Nuclear fuel rods - Accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Analysis of pin by pin effects for LWR rod ejection accident |
| Record Nr. | UNINA-9910707211503321 |
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Avvakumov A.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , March 2000 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Analysis of REALP5/MOD3.3 prediction of 2-inch loss-of-coolant accident at Krško Nuclear Power Plant [[electronic resource] /] / prepared by Itzok Parzer, Borut Mavko
| Analysis of REALP5/MOD3.3 prediction of 2-inch loss-of-coolant accident at Krško Nuclear Power Plant [[electronic resource] /] / prepared by Itzok Parzer, Borut Mavko |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , [2010] |
| Descrizione fisica | 1 online resource (viii, 41 pages) : illustrations, charts |
| Altri autori (Persone) |
ParzerIztok <1960->
MavkoBorut |
| Collana | International agreement report |
| Soggetto topico |
Nuclear reactor accidents - Slovenia - Krško
Nuclear power plants - Slovenia - Krško |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697046203321 |
| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , [2010] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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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 |
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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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