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Assessment of CCFL model of RELAP5/MOD3 against simple vertical tubes and rod bundle tests / / prepared by S. Cho [and three others]
| Assessment of CCFL model of RELAP5/MOD3 against simple vertical tubes and rod bundle tests / / prepared by S. Cho [and three others] |
| Autore | Cho S. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 1993 |
| Descrizione fisica | 1 online resource (114 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Accidents - Computer simulation
Nuclear fuel rods - Testing |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910708490003321 |
Cho S.
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| 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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Data base on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂ fuel (VVER type) under reactivity accident conditions
| Data base on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂ fuel (VVER type) under reactivity accident conditions |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 1999 |
| Descrizione fisica | 1 online resource (3 volumes) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear fuel rods - Testing
Nuclear fuel claddings - Testing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto | vol. 1. Review of research program and analysis of results / prepared by L. Yegorova -- vol. 2. Description of the test procedures and analytical methods / prepared by L. Yegorova [and sixteen others] -- vol. 3. Test and calculation results / prepared by L. Yegorova [and eighteen others]. |
| Altri titoli varianti | Data base on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂ fuel |
| Record Nr. | UNINA-9910707110403321 |
| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 1999 | ||
| 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 |
|
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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Rod bundle heat transfer test facility description [[electronic resource] /] / prepared by E.R. Rosal ... [and others] ; K. Tien, NRC project manager
| Rod bundle heat transfer test facility description [[electronic resource] /] / prepared by E.R. Rosal ... [and others] ; K. Tien, NRC project manager |
| Pubbl/distr/stampa | Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] |
| Descrizione fisica | 1 online resource (209 unnumbered pages) : illustrations |
| Altri autori (Persone) | RosalE. R |
| Soggetto topico |
Pressurized water reactors - Loss of coolant
Nuclear fuel rods - Testing Heat - Transmission |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699674803321 |
| Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Rod bundle heat transfer test facility test plan and design [[electronic resource] /] / prepared by L.E. Hochreiter ... [and others] ; K. Tien, NRC project manager
| Rod bundle heat transfer test facility test plan and design [[electronic resource] /] / prepared by L.E. Hochreiter ... [and others] ; K. Tien, NRC project manager |
| Pubbl/distr/stampa | Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] |
| Descrizione fisica | 1 online resource (568 unnumbered pages) : illustrations |
| Altri autori (Persone) | HochreiterL. E |
| Soggetto topico |
Pressurized water reactors - Loss of coolant
Nuclear fuel rods - Testing Heat - Transmission |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699674903321 |
| Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Thermal hydraulic and fuel rod mechanical combination analysis of Kuosheng Nuclear Power Plant with RELAP5 MOD3.3/FRAPTRAN/Python in SNAP interface / / prepared by Jong-Rong Wang [and five others]
| Thermal hydraulic and fuel rod mechanical combination analysis of Kuosheng Nuclear Power Plant with RELAP5 MOD3.3/FRAPTRAN/Python in SNAP interface / / prepared by Jong-Rong Wang [and five others] |
| Autore | Wang Jong-Rong |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , November 2016 |
| Descrizione fisica | 1 online resource (xv, 45 pages) : illustrations |
| 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-9910708659903321 |
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Wang Jong-Rong
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| Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , November 2016 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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