Analysis and computational predictions of CHF position and post-CHF heat transfer [[electronic resource] /] / prepared by B. Belhouachi, S.P. Walker, G.F. Hewitt
| Analysis and computational predictions of CHF position and post-CHF heat transfer [[electronic resource] /] / prepared by B. Belhouachi, S.P. Walker, G.F. Hewitt |
| Autore | Belhouachi B |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] |
| Descrizione fisica | 1 online resource (30 pages (various pagings)) : illustrations (some color) |
| Altri autori (Persone) |
WalkerS. P
HewittG. F (Geoffrey Frederick) CalvoA |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Critical heat flux - Computer simulation
Trace elements - Analysis - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697125903321 |
Belhouachi B
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| Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] | ||
| Lo trovi qui: Univ. Federico II | ||
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Analysis of a loss of normal feedwater transient at the Ringhals-3 NPP using RELAP5/Mod3.3 [[electronic resource] /] / prepared by: J. Bánáti, C. Demaziére, and M. Stålek
| Analysis of a loss of normal feedwater transient at the Ringhals-3 NPP using RELAP5/Mod3.3 [[electronic resource] /] / prepared by: J. Bánáti, C. Demaziére, and M. Stålek |
| Autore | Bánáti J (Jozsef) |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] |
| Descrizione fisica | 1 online resource (58 pages) : illustrations (some color), color map |
| Altri autori (Persone) |
DemaziéreC
StålekM CalvoA |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Control - Analysis
Nuclear power plants - Safety measures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699322803321 |
Bánáti J (Jozsef)
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| Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of RELAP5/MOD3.3Beta code for the LOFT Experiment L9-1/L3-3 [[electronic resource] /] / prepared by: Kyu Bok Lee ... [and others]
| Assessment of RELAP5/MOD3.3Beta code for the LOFT Experiment L9-1/L3-3 [[electronic resource] /] / prepared by: Kyu Bok Lee ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] |
| Descrizione fisica | 1 online resource (97 pages) : illustrations |
| Altri autori (Persone) |
LeeKyu Bok
CalvoA |
| Collana | International agreement report |
| Soggetto topico |
Nuclear reactor accidents - Evaluation
Nuclear power plants - Accidents - Evaluation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697290803321 |
| Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of the TRACE code using transient data from Maanshan PWR Nuclear Power Plant [[electronic resource] /] / prepared by: Jong-Rong Wang, Hao-Tzu Lin, Chunkuan Shih
| Assessment of the TRACE code using transient data from Maanshan PWR Nuclear Power Plant [[electronic resource] /] / prepared by: Jong-Rong Wang, Hao-Tzu Lin, Chunkuan Shih |
| Autore | Wang Jong-Rong |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] |
| Descrizione fisica | 1 online resource (54 pages) : illustrations (some color) |
| Altri autori (Persone) |
LinHao-Tzu
ShihChunkuan CalvoA |
| Collana | International agreement report |
| Soggetto topico |
Nuclear power plants - Instruments - Control
Nuclear engineering - Instruments |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699323303321 |
Wang Jong-Rong
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| Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of the turbine trip transient in Santa Maria de Garoña Nuclear Power Plant with TRACE version 4.16 [[electronic resource] /] / prepared by: P. Corcuera, E. Rodríguez, G. Villescas
| Assessment of the turbine trip transient in Santa Maria de Garoña Nuclear Power Plant with TRACE version 4.16 [[electronic resource] /] / prepared by: P. Corcuera, E. Rodríguez, G. Villescas |
| Autore | Corcuera P |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] |
| Descrizione fisica | 1 online resource (46 pages) : illustrations |
| Altri autori (Persone) |
RodríguezE
VillescasG CalvoAntony |
| Collana | International agreement report |
| Soggetto topico |
Nuclear reactor accidents - Spain - Computer simulation
Nuclear engineering - Spain - Instruments - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697046503321 |
Corcuera P
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| Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] | ||
| Lo trovi qui: Univ. Federico II | ||
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An assessment of TRACE V4.160 code against PACTEL ATWS-10 - 13 and ATWS-20 - 21 pressurizer experiments [[electronic resource] /] / prepared by: E. Takasuo
| An assessment of TRACE V4.160 code against PACTEL ATWS-10 - 13 and ATWS-20 - 21 pressurizer experiments [[electronic resource] /] / prepared by: E. Takasuo |
| Autore | Takasuo E |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] |
| Descrizione fisica | 1 online resource (vii, 23, 18 pages) : illustrations |
| Altri autori (Persone) | CalvoA |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Control - Simulation methods
Nuclear engineering - Instruments - Simulation methods |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697291203321 |
Takasuo E
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| Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] | ||
| Lo trovi qui: Univ. Federico II | ||
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An assessment of TRACE V4.160 code against PACTEL LOF-10 experiment [[electronic resource] /] / prepared by: J. Vihavainen
| An assessment of TRACE V4.160 code against PACTEL LOF-10 experiment [[electronic resource] /] / prepared by: J. Vihavainen |
| Autore | Vihavainen J (Juhani) |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] |
| Descrizione fisica | 1 online resource (151 pages) : illustrations (some color) |
| Altri autori (Persone) | CalvoA |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Control - Analysis
Nuclear engineering - Instruments - Analysis |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699323003321 |
Vihavainen J (Juhani)
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| Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] | ||
| Lo trovi qui: Univ. Federico II | ||
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Benchmarking of a generic CANDU reactor with PARCS, MCNP and RFSP / / prepared by B. Arsenault [and five others]
| Benchmarking of a generic CANDU reactor with PARCS, MCNP and RFSP / / prepared by B. Arsenault [and five others] |
| Autore | Arsenault B. |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, , September 2015 |
| Descrizione fisica | 1 online resource (93 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
CANDU reactors - Computer simulation - Quality control
Heavy water reactors - Computer simulation - Quality control |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910704091503321 |
Arsenault B.
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| Washington, DC : , : U. S. Nuclear Regulatory Commission, , September 2015 | ||
| Lo trovi qui: Univ. Federico II | ||
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The development and assessment of TRACE model for Maanshan Nuclear Power Plant LOCA / / prepared by: Jong-Rong Wang [and three others]
| The development and assessment of TRACE model for Maanshan Nuclear Power Plant LOCA / / prepared by: Jong-Rong Wang [and three others] |
| Autore | Wang Jong-Rong |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2012] |
| Descrizione fisica | 1 online resource (49 pages) : colored illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - China - Loss of coolant - Computer simulation
Pressurized water reactors - Accidents - China - Computer simulation Nuclear power plants - China - Computer simulation Nuclear power plants - China - Safety measures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Development and assessment of TRAC/RELAP Advanced Computational Engine model for Maanshan PWR Nuclear Power Plant Loss of Coolant Accident |
| Record Nr. | UNINA-9910704351103321 |
Wang Jong-Rong
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| Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2012] | ||
| Lo trovi qui: Univ. Federico II | ||
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Development of horizontal off-take model for application to reactor headers of CANDU type reactors [[electronic resource] /] / prepared by: Yong Jin Cho ... [and others]
| Development of horizontal off-take model for application to reactor headers of CANDU type reactors [[electronic resource] /] / prepared by: Yong Jin Cho ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] |
| Descrizione fisica | 1 online resource (61 pages) : illustrations |
| Altri autori (Persone) |
ChoYŏng-jin
CalvoA |
| Collana | International agreement report |
| Soggetto topico |
CANDU reactors - Accidents - Analysis
Nuclear reactor accidents - Analysis Nuclear reactors - Fluid dynamics - Models |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699323103321 |
| Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] | ||
| Lo trovi qui: Univ. Federico II | ||
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