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Analysis of the LOBI experiment test BT-56 using the RELAP5/MOD3.2 code / / prepared by J. Blanco [and three others]
| Analysis of the LOBI experiment test BT-56 using the RELAP5/MOD3.2 code / / prepared by J. Blanco [and three others] |
| Autore | Blanco J. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 2000 |
| Descrizione fisica | 1 online resource (xiii, 55 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear reactor accidents - Computer simulation
Pressurized water reactors - Accidents - Computer simulation |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910706151303321 |
Blanco J.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 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]
| 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 |
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Seul K. W.
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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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Assessment study on the PMK-2 total loss of feedwater experiment using RELAP5 code / / prepared by J. Bánáti
| 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 |
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Bánáti J (Jozsef)
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| 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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Coupling the RELAP code with external calculation programs (shared memory version) [[electronic resource] /] / prepared by Felix Maciel
| Coupling the RELAP code with external calculation programs (shared memory version) [[electronic resource] /] / prepared by Felix Maciel |
| Autore | Maciel Felix |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2011] |
| Descrizione fisica | 1 online resource (15 unnumbered pages) : illustrations |
| 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 |
| Altri titoli varianti | Coupling the RELAP code with external calculation programs |
| Record Nr. | UNINA-9910701383803321 |
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Maciel Felix
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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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Developmental assessment of RELAP5/MOD3.1 with separate-effect and integral test experiments : model changes and options / / prepared by G. Th. Analytis
| Developmental assessment of RELAP5/MOD3.1 with separate-effect and integral test experiments : model changes and options / / prepared by G. Th. Analytis |
| Autore | Analytis G. Th (Gerassimos Th.) |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , October 1998 |
| Descrizione fisica | 1 online resource (v, 39 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 |
| Altri titoli varianti | Developmental assessment of RELAP5/MOD3.1 with separate-effect and integral test experiments |
| Record Nr. | UNINA-9910705828803321 |
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Analytis G. Th (Gerassimos Th.)
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , October 1998 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Full scale loop seal experiments with TRACE V5 Patch 1 [[electronic resource] /] / prepared by Seppo Hillberg
| Full scale loop seal experiments with TRACE V5 Patch 1 [[electronic resource] /] / prepared by Seppo Hillberg |
| Autore | Hillberg S |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2011] |
| Descrizione fisica | 1 online resource (vii, 13 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Water-pipes - Accidents - Computer simulation
Nuclear power plants - Accidents - Computer simulation Nuclear reactor accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910701383903321 |
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Hillberg S
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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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MACCS best practices as applied in the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project / / prepared by Nathan Bixler [and three others]
| MACCS best practices as applied in the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project / / prepared by Nathan Bixler [and three others] |
| Autore | Bixler N. E (Nathan E.) |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , 2014 |
| Descrizione fisica | 1 online resource (197 unnumbered pages) : color illustrations |
| Soggetto topico |
Nuclear power plants - Accidents - Computer simulation
Nuclear reactor accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | MACCS best practices as applied in the State-of-the-Art Reactor Consequence Analyses |
| Record Nr. | UNINA-9910702693503321 |
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Bixler N. E (Nathan E.)
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Main stream line break analysis for lungmen ABWR / / prepared by Chunkuan Shih [and five others]
| Main stream line break analysis for lungmen ABWR / / prepared by Chunkuan Shih [and five others] |
| Autore | Shih Chunkuan |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 2016 |
| Descrizione fisica | 1 online resource (xiii, 24 pages) : illustrations + + errata |
| 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-9910708659703321 |
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Shih Chunkuan
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| Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 2016 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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MELCOR best practices as applied in the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project / / prepared by Kyle Ross [and three others]
| MELCOR best practices as applied in the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project / / prepared by Kyle Ross [and three others] |
| Autore | Ross Kyle |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , 2014 |
| Descrizione fisica | 1 online resource (133 unnumbered pages) : color illustrations |
| Soggetto topico |
Nuclear power plants - Accidents - Computer simulation
Nuclear reactor accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | MELCOR best practices as applied in the State-of-the-Art Reactor Consequence Analyses |
| Record Nr. | UNINA-9910702693603321 |
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Ross Kyle
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Modeling potential reactor accident consequences
| Modeling potential reactor accident consequences |
| Pubbl/distr/stampa | Washington, D.C. : , : U.S. Nuclear Regulatory Commission, , [2012] |
| Descrizione fisica | 1 online resource (vii, 47 pages) : colored illustrations, maps |
| Collana | NUREG/BR |
| Soggetto topico |
Nuclear reactor accidents - Computer simulation
Nuclear power plants - Accidents - Health aspects Nuclear facilities - Accidents Radiation - Health aspects |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910701874603321 |
| Washington, D.C. : , : U.S. Nuclear Regulatory Commission, , [2012] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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