Monte Carlo proračun spregnutog neutron-gama transporta za određivanje brzine doze primarnog kruga PWR reaktora i kontejnmenta (SCALE6.1 programski paket razvijen u Oak Ridge National Laboratory, USA)
Monte Carlo proračun spregnutog neutron-gama transporta za određivanje brzine doze homogeniziranog spremnika za istrošene gorivne elemente reaktora (MCNP6.1 programski paket razvijen u Los Alamos National Laboratory, USA )
Deterministički proračun metodom diskretnih ordinata (S6/P1, anisn_library 27n19g) za polje fotona unutar kontejnmenta PWR reaktora - riješenje adjungirane transportne jednadžbe za optimizaciju točkastih detektora
(ADVANTG 3.0.1 programski paket razvijen u Oak Ridge National Laboratory, USA )
Usporedba determinističkog (slika lijevo) i Monte Carlo proračuna (desno) polja fotona iznad bazena za istrošene gorivne elemente PWR reaktora (ADVANTG 3.0.1 i MCNP6.1 programski paketi, USA )
Monte Carlo proračun brzine neutronske doze na tlačnu posudu integralnog reaktora (MCNP6.1 programski paket, USA )
*** Izvorni znanstveni radovi objavljeni u CC časopisima ***
1. Matijević, Mario; Pevec, Dubravko; Trontl, Krešimir.
Boration modeling of the PWR biological shield using SCALE6.1 hybrid shielding methodology.
//Annals of nuclear energy, Vol. 85 (2015), 979-994.
2. Matijević, Mario; Pevec, Dubravko; Trontl, Krešimir.
PWR Containment Shielding Calculations with SCALE6.1 Using Hybrid Deterministic-Stochastic Methodology.
// Science and Technology of Nuclear Installations
Volume 2016 (2016), Article ID 7328131, 30 pages
*** Znanstveni radovi u zbornicima skupova s međunarodnom recenzijom ***
1. Matijević, Mario; Grgić, Davor; Pevec, Dubravko.
Severe accident gamma dose distribution through NPP Krško containment and auxiliary building calculated using SCALE6/MAVRIC sequence // Proceedings of the 24th International Conference Nuclear Energy for New Europe / Jenčič, Igor (ur.) Ljubljana : Nuclear Society of Slovenia (2015), 411.1-411.13.
2. Dučkić, Paulina; Trontl, Krešimir; Matijević, Mario.
Active learning for support vector regression in radiation shielding design // Proceedings of the 2015 International Conference on High Performance Computing & Simulation (HPCS 2015) / Smari, Waleed W. ; Zeljkovic, Vesna (ur.). Amsterdam : IEEE, 2015. 311-317.
3. Matijević, Mario; Pevec, Dubravko; Trontl, Krešimir.
Modeling of PWR Biological Shield Boration Using SCALE6.1 Hybrid Shielding Methodology // 23rd International Conference Nuclear Energy for New Europe Proceedings / Igor Jenčić (ur.). Slovenija : Nuclear Society of Slovenia (2014), 607.1-607.15.
4. Matijević, Mario; Pevec, Dubravko; Ječmenica, Radomir
I2S-LWR Activation Analysis of Heat Exchangers Using Hybrid Shielding Methodology With SCALE6.1 // 11th International Conference of the Croatian Nuclear Society Proceedings / Šimić, Zdenko; Tomšić, Željko; Grgić, Davor (ur.) Zagreb : Croatian Nuclear Society (2016), 64-1 - 64-12.
5. Dučkić, Paulina; Matijević, Mario; Grgić, Davor
Neutron Buildup Factors Calculation for Support Vector Regression Application in Shielding Analysis
// 11th International Conference of the Croatian Nuclear Society Proceedings / Šimić, Zdenko; Tomšić, Željko; Grgić, Davor (ur.) Zagreb : Croatian Nuclear Society (2016), 051-1 - 051-11.
6. Matijević, Mario; Pevec, Dubravko; Trontl, Krešimir
I2S-LWR Pressure Vessel Fast Fluence Calculations //Proceedings of the 25th International Conference Nuclear Energy for New Europe NENE2016 / Snoj, Luka ; Lengar, Igor (ur.). - Ljubljana : Nuclear Society of Slovenia , 2016. 301.1-301.14 (ISBN: 978-961-6207-39-3).
*** Radovi u zbornicima skupova bez recenzije ***
1. Dučkić, Paulina; Trontl, Krešimir; Pevec, Dubravko.
RESEARCH AND DEVELOPMENT OF POINT-KERNEL METHOD APPLICATION IN RADIATION SHIELDING // Proceedings of the 10th Symposium of the CROATIAN RADIATION PROTECTION ASSOCIATION / Petrinec, Branko ; Bituh, Tomislav ; Milić, Mirta ; Kopjar, Nevenka (ur.). Zagreb : CROATIAN RADIATION PROTECTION ASSOCIATION, 2015. 402-407.
2. Matijević, Mario; Pevec, Dubravko; Trontl, Krešimir.
SCALE6.1 HYBRID SHIELDING METHODOLOGY FOR THE SPENT FUEL DRY STORAGE // Proceedings of the 10th Symposium of the CROATIAN RADIATION PROTECTION ASSOCIATION / Petrinec, Branko ; Bituh, Tomislav ; Milić, Mirta ; Kopjar, Nevenka (ur.). Zagreb : CROATIAN RADIATION PROTECTION ASSOCIATION, 2015. 408-413.