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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] | ||
| Materiale a stampa | ||
| 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 |
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Bánáti J (Jozsef)
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| Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of RELAP5/MOD3.3 against single main steam isolation valve closure events at the Krško Nuclear Power Plant [[electronic resource] /] / prepared by I. Parzer, B. Mavko, A. Calvo
| Assessment of RELAP5/MOD3.3 against single main steam isolation valve closure events at the Krško Nuclear Power Plant [[electronic resource] /] / prepared by I. Parzer, B. Mavko, A. Calvo |
| Autore | Parzer Iztok <1960-> |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2010] |
| Descrizione fisica | 1 online resource (vii, 25 pages) : illustrations, charts |
| Altri autori (Persone) |
MavkoBorut
CalvoA |
| Collana | International agreement report |
| Soggetto topico |
Nuclear reactor accidents - Slovenia - Krško
Nuclear power plants - Accidents - Slovenia - Krško |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697046303321 |
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Parzer Iztok <1960->
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2010] | ||
| Materiale a stampa | ||
| 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] | ||
| Materiale a stampa | ||
| 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 |
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Wang Jong-Rong
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| Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] | ||
| Materiale a stampa | ||
| 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 |
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Takasuo E
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| Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] | ||
| Materiale a stampa | ||
| 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 |
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Vihavainen J (Juhani)
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| Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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An assessment of TRACE V5 RC1 code separator model with the Westinghouse Model Boiler 2 experiments [[electronic resource] /] / prepared by S. Hillberg, A. Calvo
| An assessment of TRACE V5 RC1 code separator model with the Westinghouse Model Boiler 2 experiments [[electronic resource] /] / prepared by S. Hillberg, A. Calvo |
| Autore | Hillberg S |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2010] |
| Descrizione fisica | 1 online resource (32 pages) : illustrations |
| Altri autori (Persone) | CalvoA |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Control
Nuclear engineering - Instruments |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697046403321 |
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Hillberg S
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2010] | ||
| Materiale a stampa | ||
| 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] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Numerical analysis of mixing factors in the RPV of VVER-440 reactor using the TRACE code [[electronic resource] /] / prepared by: Petr Heralecky, Martin Blaha
| Numerical analysis of mixing factors in the RPV of VVER-440 reactor using the TRACE code [[electronic resource] /] / prepared by: Petr Heralecky, Martin Blaha |
| Autore | Heralecky P (Petr) |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] |
| Descrizione fisica | 1 online resource (80 pages) : illustrations |
| Altri autori (Persone) |
BlahaMartin
CalvoA |
| Collana | International agreement report |
| Soggetto topico |
Nuclear power plants - Safety measures
Water cooled reactors - Loss of coolant - Safety measures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697125603321 |
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Heralecky P (Petr)
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| Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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