Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER Facility
The OECD/NEA PSB-VVER project provided unique and useful experimental data for code validation from PSB-VVER test facility. This facility represents the scaled-down layout of the Russian-designed pressurized water reactor, namely, VVER-1000. Five experiments were executed, dealing with loss of coola...
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| Format: | Article |
| Language: | English |
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Wiley
2012-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2012/480948 |
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| author | A. Del Nevo M. Adorni F. D'Auria O. I. Melikhov I. V. Elkin V. I. Schekoldin M. O. Zakutaev S. I. Zaitsev M. Benčík |
| author_facet | A. Del Nevo M. Adorni F. D'Auria O. I. Melikhov I. V. Elkin V. I. Schekoldin M. O. Zakutaev S. I. Zaitsev M. Benčík |
| author_sort | A. Del Nevo |
| collection | DOAJ |
| description | The OECD/NEA PSB-VVER project provided unique and useful experimental data for code validation from PSB-VVER test facility. This facility represents the scaled-down layout of the Russian-designed pressurized water reactor, namely, VVER-1000. Five experiments were executed, dealing with loss of coolant scenarios (small, intermediate, and large break loss of coolant accidents), a primary-to-secondary leak, and a parametric study (natural circulation test) aimed at characterizing the VVER system at reduced mass inventory conditions. The comparative analysis, presented in the paper, regards the large break loss of coolant accident experiment. Four participants from three different institutions were involved in the benchmark and applied their own models and set up for four different thermal-hydraulic system codes. The benchmark demonstrated the performances of such codes in predicting phenomena relevant for safety on the basis of fixed criteria. |
| format | Article |
| id | doaj-art-e7ad943862cf478ab505d0bc05fb99fa |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2012-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-e7ad943862cf478ab505d0bc05fb99fa2025-02-03T05:44:29ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832012-01-01201210.1155/2012/480948480948Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER FacilityA. Del Nevo0M. Adorni1F. D'Auria2O. I. Melikhov3I. V. Elkin4V. I. Schekoldin5M. O. Zakutaev6S. I. Zaitsev7M. Benčík8GRNSPG, University of Pisa, Livornese street 1291, San Piero a Grado, 56126 Pisa, ItalyGRNSPG, University of Pisa, Livornese street 1291, San Piero a Grado, 56126 Pisa, ItalyGRNSPG, University of Pisa, Livornese street 1291, San Piero a Grado, 56126 Pisa, ItalyTH Division, Electrogorsk Research and Engineering Centre, Elektrogorsk, RussiaTH Division, Electrogorsk Research and Engineering Centre, Elektrogorsk, RussiaFSUE EDO “GIDROPRESS”, Podolsk, RussiaFSUE EDO “GIDROPRESS”, Podolsk, RussiaFSUE EDO “GIDROPRESS”, Podolsk, RussiaTH Analyses Department, Nuclear Research Institute Řež, 250 68 Řež, Czech RepublicThe OECD/NEA PSB-VVER project provided unique and useful experimental data for code validation from PSB-VVER test facility. This facility represents the scaled-down layout of the Russian-designed pressurized water reactor, namely, VVER-1000. Five experiments were executed, dealing with loss of coolant scenarios (small, intermediate, and large break loss of coolant accidents), a primary-to-secondary leak, and a parametric study (natural circulation test) aimed at characterizing the VVER system at reduced mass inventory conditions. The comparative analysis, presented in the paper, regards the large break loss of coolant accident experiment. Four participants from three different institutions were involved in the benchmark and applied their own models and set up for four different thermal-hydraulic system codes. The benchmark demonstrated the performances of such codes in predicting phenomena relevant for safety on the basis of fixed criteria.http://dx.doi.org/10.1155/2012/480948 |
| spellingShingle | A. Del Nevo M. Adorni F. D'Auria O. I. Melikhov I. V. Elkin V. I. Schekoldin M. O. Zakutaev S. I. Zaitsev M. Benčík Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER Facility Science and Technology of Nuclear Installations |
| title | Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER Facility |
| title_full | Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER Facility |
| title_fullStr | Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER Facility |
| title_full_unstemmed | Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER Facility |
| title_short | Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER Facility |
| title_sort | validation of advanced computer codes for vver technology lb loca transient in psb vver facility |
| url | http://dx.doi.org/10.1155/2012/480948 |
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