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Pregled bibliografske jedinice broj: 941884

NPP Krško 3 inch Cold Leg Break LOCA Calculation using RELAP5/MOD 3.3 and MELCOR 1.8.6 Codes


Benčik, Vesna; Grgić, Davor; Šadek, Siniša; Vlahović, Štefica
NPP Krško 3 inch Cold Leg Break LOCA Calculation using RELAP5/MOD 3.3 and MELCOR 1.8.6 Codes // 12th International Conference of the Croatian Nuclear Society Conference Proceedings / Vrbanić, Ivan ; Šadek, Siniša ; Bašić, Ivica (ur.).
Zagreb: Hrvatsko nuklearno društvo, 2018. str. S5-142-1-S5-142-14 (poster, međunarodna recenzija, cjeloviti rad (in extenso), znanstveni)


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Naslov
NPP Krško 3 inch Cold Leg Break LOCA Calculation using RELAP5/MOD 3.3 and MELCOR 1.8.6 Codes

Autori
Benčik, Vesna ; Grgić, Davor ; Šadek, Siniša ; Vlahović, Štefica

Vrsta, podvrsta i kategorija rada
Radovi u zbornicima skupova, cjeloviti rad (in extenso), znanstveni

Izvornik
12th International Conference of the Croatian Nuclear Society Conference Proceedings / Vrbanić, Ivan ; Šadek, Siniša ; Bašić, Ivica - Zagreb : Hrvatsko nuklearno društvo, 2018, S5-142-1-S5-142-14

ISBN
978-953-48100-0-2

Skup
12th International Conference of the Croatian Nuclear Society

Mjesto i datum
Zadar, Hrvatska, 03.06.2018. - 06.06.2018

Vrsta sudjelovanja
Poster

Vrsta recenzije
Međunarodna recenzija

Ključne riječi
MELCOR, RELAP5, code comparison, input data verification, small break Loss of Coolant Accident

Sažetak
NPP Krško input deck developed at Faculty of Electrical Engineering and Computing (FER) Zagreb, for severe accident code MELCOR 1.8.6 is currently being tested. MELCOR is primarily used for the analyses of severe accidents including in-vessel and ex-vessel core melt progression as well as containment response under severe accident conditions. Accurate modelling of the plant thermal-hydraulic behaviour as well as engineering safety features, e.g., Emergency Core Cooling System, Auxiliary feedwater system and various containment systems (e.g., Passive Autocatalytic Recombiners, Fan Coolers and Containment spray) is necessary to correctly predict the plant response and operator actions. For MELCOR input data verification, the comparison of the results for small break (3 inch) cold leg Loss of Coolant Accident (LOCA) for NPP Krško using MELCOR 1.8.6 and RELAP5/MOD 3.3 was performed. A detailed RELAP5/MOD 3.3 model for NPP Krško has been developed at FER and it has been extensively used for accident and transient analyses. The RELAP5 model has been upgraded and improved along with the plant modernization in the year 2000. and after more recent plant modifications. The results of the steady state calculation (first 1000 seconds) for both MELCOR and RELAP5 were assessed against the referent plant data. In order to test all thermal-hydraulic aspects of developed MELCOR 1.8.6 model the accident was analysed, and comparison to the existing RELAP5 model was performed, with all engineering safety features available. After initial fast pressure drop and accumulator injection for both codes stable conditions were established with heat removal through the break and core inventory maintained by safety injection. Transient was simulated for 10000 seconds and overall good agreement between results obtained with both codes was found.

Izvorni jezik
Engleski



POVEZANOST RADA


Ustanove:
Fakultet elektrotehnike i računarstva, Zagreb

Profili:

Avatar Url Štefica Vlahović (autor)

Avatar Url Davor Grgić (autor)

Avatar Url Vesna Benčik (autor)

Avatar Url Siniša Šadek (autor)


Citiraj ovu publikaciju:

Benčik, Vesna; Grgić, Davor; Šadek, Siniša; Vlahović, Štefica
NPP Krško 3 inch Cold Leg Break LOCA Calculation using RELAP5/MOD 3.3 and MELCOR 1.8.6 Codes // 12th International Conference of the Croatian Nuclear Society Conference Proceedings / Vrbanić, Ivan ; Šadek, Siniša ; Bašić, Ivica (ur.).
Zagreb: Hrvatsko nuklearno društvo, 2018. str. S5-142-1-S5-142-14 (poster, međunarodna recenzija, cjeloviti rad (in extenso), znanstveni)
Benčik, V., Grgić, D., Šadek, S. & Vlahović, Š. (2018) NPP Krško 3 inch Cold Leg Break LOCA Calculation using RELAP5/MOD 3.3 and MELCOR 1.8.6 Codes. U: Vrbanić, I., Šadek, S. & Bašić, I. (ur.)12th International Conference of the Croatian Nuclear Society Conference Proceedings.
@article{article, author = {Ben\v{c}ik, Vesna and Grgi\'{c}, Davor and \v{S}adek, Sini\v{s}a and Vlahovi\'{c}, \v{S}tefica}, year = {2018}, pages = {S5-142-1-S5-142-14}, keywords = {MELCOR, RELAP5, code comparison, input data verification, small break Loss of Coolant Accident}, isbn = {978-953-48100-0-2}, title = {NPP Kr\v{s}ko 3 inch Cold Leg Break LOCA Calculation using RELAP5/MOD 3.3 and MELCOR 1.8.6 Codes}, keyword = {MELCOR, RELAP5, code comparison, input data verification, small break Loss of Coolant Accident}, publisher = {Hrvatsko nuklearno dru\v{s}tvo}, publisherplace = {Zadar, Hrvatska} }
@article{article, author = {Ben\v{c}ik, Vesna and Grgi\'{c}, Davor and \v{S}adek, Sini\v{s}a and Vlahovi\'{c}, \v{S}tefica}, year = {2018}, pages = {S5-142-1-S5-142-14}, keywords = {MELCOR, RELAP5, code comparison, input data verification, small break Loss of Coolant Accident}, isbn = {978-953-48100-0-2}, title = {NPP Kr\v{s}ko 3 inch Cold Leg Break LOCA Calculation using RELAP5/MOD 3.3 and MELCOR 1.8.6 Codes}, keyword = {MELCOR, RELAP5, code comparison, input data verification, small break Loss of Coolant Accident}, publisher = {Hrvatsko nuklearno dru\v{s}tvo}, publisherplace = {Zadar, Hrvatska} }




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