Info
- Utilizzare la checkbox di selezione a fianco di ciascun documento per attivare le funzionalità di stampa, invio email, download nei formati disponibili del (i) record.
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.
|
||
| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 2001 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Analysis of the THETIS boildown experiments using RELAP5/MOD2 / / prepared by M.G. Croxford, P.C. Hall
| Analysis of the THETIS boildown experiments using RELAP5/MOD2 / / prepared by M.G. Croxford, P.C. Hall |
| Autore | Croxford M. G. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 1989 |
| Descrizione fisica | 1 online resource (9, 35 unnumbered pages) : 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-9910707646203321 |
|
Croxford M. G.
|
||
| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 1989 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Analysis of the VTI test data on the behavior of the heated rod temperatures in the partially uncovered VVER-440 core model using RELAP5/MOD3.2.2 gamma / / prepared by V.A. Vinogradov, and A.Y. Balykin
| Analysis of the VTI test data on the behavior of the heated rod temperatures in the partially uncovered VVER-440 core model using RELAP5/MOD3.2.2 gamma / / prepared by V.A. Vinogradov, and A.Y. Balykin |
| Autore | Vinogradov V. A. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 2002 |
| 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-9910706113603321 |
|
Vinogradov V. A.
|
||
| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 2002 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Assessment of RELAP5/MOD2 computer code against the natural circulation test data from Yong-Gwang unit 2 / / prepared by N. Arne, S. Cho, H.J. Kim
| Assessment of RELAP5/MOD2 computer code against the natural circulation test data from Yong-Gwang unit 2 / / prepared by N. Arne, S. Cho, H.J. Kim |
| Autore | Arne N. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 1993 |
| Descrizione fisica | 1 online resource (iii, 50, 50 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear power plants - Accidents - Korea (South) - Computer simulation
Pressurized water reactors - Loss of coolant - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707851603321 |
|
Arne N.
|
||
| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 1993 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Assessment of RELAP5/MOD3 with the SNUF test simulating hot leg break LOCA in the view of mass and energy release analysis / / prepared by S. Joon Hong [and three others]
| Assessment of RELAP5/MOD3 with the SNUF test simulating hot leg break LOCA in the view of mass and energy release analysis / / prepared by S. Joon Hong [and three others] |
| Autore | Hong S. Joon |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , February 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-9910706146003321 |
|
Hong S. Joon
|
||
| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , February 2001 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Assessment of RELAP5/MOD3.2 for steam condensation experiments in the presence of noncondensibles in a vertical tube of PCCS / / prepared by H. S. Park [and five others]
| Assessment of RELAP5/MOD3.2 for steam condensation experiments in the presence of noncondensibles in a vertical tube of PCCS / / prepared by H. S. Park [and five others] |
| Autore | Park Hyeon-Sook |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , September 1998 |
| Descrizione fisica | 1 online resource (xvii, 91 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Condensation - Computer simulation
Pressurized water reactors - Loss of coolant - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910705830503321 |
|
Park Hyeon-Sook
|
||
| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , September 1998 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Assessment of RELAP5/MOD3.2 using LOFT large break LOCA test, LP-02-6 / / prepared by T.S. Choi [and seven others]
| Assessment of RELAP5/MOD3.2 using LOFT large break LOCA test, LP-02-6 / / prepared by T.S. Choi [and seven others] |
| Autore | Choi T. S. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 1998 |
| Descrizione fisica | 1 online resource (vi, 68, A38 pages) : 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-9910705829003321 |
|
Choi T. S.
|
||
| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 1998 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Assessment of RELAP5/MOD3.2 with the semiscale natural circulation experiment, S-NC-8B / / prepared by Y.S. Bang [and three others]
| Assessment of RELAP5/MOD3.2 with the semiscale natural circulation experiment, S-NC-8B / / prepared by Y.S. Bang [and three others] |
| Autore | Bang Y. S (Young Seok) |
| 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 | Pressurized water reactors - Loss of coolant - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910705827203321 |
|
Bang Y. S (Young Seok)
|
||
| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 1998 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Assessment of RELAP5/MOD3.3 and TRACE V5.0 computer codes against LOCA test data from PSB-VVER test facility / / prepared by M. Kynčl, R. Pernica
| Assessment of RELAP5/MOD3.3 and TRACE V5.0 computer codes against LOCA test data from PSB-VVER test facility / / prepared by M. Kynčl, R. Pernica |
| Autore | Kynčl M. |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, , 2013 |
| Descrizione fisica | 1 online resource (xvi, 183 pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant - Computer simulation
Nuclear facilities - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910705176703321 |
|
Kynčl M.
|
||
| Washington, DC : , : United States Nuclear Regulatory Commission, , 2013 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Assessment of TRACE 5.0 against ROSA test 3-1, cold leg SBLOCA [[electronic resource] /] / prepared by S. Gallardo ... [and others]
| Assessment of TRACE 5.0 against ROSA test 3-1, cold leg SBLOCA [[electronic resource] /] / prepared by S. Gallardo ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2012] |
| Descrizione fisica | 1 online resource (65 unnumbered pages) : color illustrations |
| Altri autori (Persone) | GallardoS |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant - Computer simulation
Nuclear power plants - Accidents - Computer simulation Nuclear power plants - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910701786803321 |
| Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2012] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
