Mavko, Borut
Borut Mavko physicien slovène
VIAF ID: 41497303 ( Personal )
Permalink: http://viaf.org/viaf/41497303
Preferred Forms
- 100 0 _ ‡a Borut Mavko ‡c physicien slovène
- 100 1 _ ‡a Mavko, Borut
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- 100 1 _ ‡a Mavko, Borut
- 100 1 _ ‡a Mavko, Borut
- 100 1 _ ‡a Mavko, Borut
4xx's: Alternate Name Forms (9)
Works
Title | Sources |
---|---|
Accuracy Quantification of BETHSY 9.1b Test | |
Analiza šuma moči reaktorja triga | |
Analiza termodinamičnih značilnosti jedrskih elektrarn | |
The analysis of operator actions during the accident caused by total loss of secondary heat sink | |
Angleško-slovenski slovarček izrazov iz jedrske tehnike | |
CFD simulation of containment atmosphere interaction with a passive autocatalytic recombiner : SARNET CAM PARIS benchmark | |
Collection of human reliability data | |
Complete loss of AC power at low pressure in Krško NPP | |
Computer managed emergency operating procedures | |
Določanje varnostne pomembnosti sprememb jedrskega objekta : magistrsko delo | |
DrAlf - program za grafično predstavitev rezultatov termohidravličnih simulacij | |
The evaluation of research reactor TRIGA MARK II safety | |
Handbook of the degradation of steam generator tubes in Krško NPP. | |
Implementation of ISP-27 BETHSY transient scenario in accident analysis for Krško NPP | |
Izjava za ponovno obratovanje NE Krško po remontu 2004 in menjavi goriva po zaključenem 20. gorivnem ciklu v NE Krško | |
Jedrska energetika | |
KONSTRUKCIJSKE,OBRATOVALNE IN VARNOSTNE ZNACILNOSTI JEDRSKIH REAKTORJEV. | |
Loss of external load analysis with RELAP5/MOD3.3 patch 03 code | |
The meaning of conservative approach in nuclear safety analyses | |
A method for rapid vulnerability assessment of structures loaded by outside blasts | |
Mixture continuum formulation of convection-conduction energy transport in multiconstituent solid-liquid phase change systems for BEM solution techniques | |
Nuclear energy for new Europe | |
Nuclear Option in Countries with Small and Medium Electricity Grids | |
An object-based approach to modelling and analysis of failure properties | |
OECD international standard problem No. 46 "PHEBUS" : simulation of FPT1 test containment phase with the CONTAIN computer code | |
On test and maintenance - optimization of allowed outage time | |
On the risk-based steam generator lifetime optimisation | |
Pregled nesreče v jedrski elektrarni Černobil | |
Preračun prehodnega pojava z izgubo napajalne vode na eksperimentalni napravi SPES | |
Proceedings | |
PWR low pressure natural circulation and loss of all AC power | |
Quantitative code assessment with improved FFTBM by signal mirroring | |
Raziskava razpoložljivosti sistema električnega napajanja z uporabo verjetnostnih varnostnih metod | |
Reactor trip analysis at Krško NPP | |
Reliability of steam generator tubes with axial cracks | |
Safety and reliability problems in chemical plant recognized during preoperational phase and operating experience backfiting | |
Safety of complex technologies : Jožef Stefan Institute, Reactor engineering division | |
SIMUL - programski paket za simulacijo zveznih sistemov | |
Simulacija jedrske elektrarne in njene obratovalne značilnosti : poročilo o raziskovalni nalogi za leto 1976 | |
Simulation of boiling flow experiments close to CHF with the Neptune_CFD code | |
Simulation of containment thermal-hydraulic transients in different facilities with the CONTAIN code | |
Simulation of KAEVER experiments on aerosol behaviour with the ASTEC CPA V1.2.code : 6th EU Framework programme SARNET ASTEC topic, WP3 PHYMA Physical model assessment | |
Simulation of void fraction profile evolution in subcooled nucleate boiling in a vertical annulus with a bubble-tracking model | |
Simulator najvažnejših procesov v jedrski elektrarni | |
Sistem oriented PSA | |
Split reactor vessel model for asymmetrical transient calculation | |
Statistic method used for LB LOCA PCT calculation | |
Status of CAMP activities in Slovenia | |
Strokovna ocena glavne napajalne vode NE Krško | |
Strokovna ocena spremembe tehničnih specifikacij NE Krško zaradi spremembe zahtev za blažilnike sunkov | |
Strokovno mnenje za poročilo "NEK Periodic Safety Review-Summary Report" | |
Suverenost energetike je povezana s suverenimi ljudmi : pogovor s člani Inženirske akademije Slovenije | |
Tehnologija jedrskega goriva in obratovanje jedrskih naprav - II. del | |
Tehnološke in varnostne značilnosti sistemov in goriva jedrske elektrarne tipa VVER-1000 | |
Thermal-hydraulic safety analyses supporting the steam generator replacement and uprating at Krško nuclear power plant | |
(A)tool for drawing with Excel | |
Training program for improved professional performance of subcontractors : project NEPTUNO | |
Uncertanity analysis of the large break loss of coolant accident | |
Uporaba verjetnostnih varnostnih analiz za izboljšanje zanesljivosti računalniških sistemov, povezanih z varnostjo | |
Upward flame propagation experiment on hydrogen combustion | |
User effect on the IAEA-SPE-4 calculation | |
Varnostne analize. | |
Verovatnostna analiza sigurnosti i pouzdanosti rada nuklearne elektrane - sistem za prinudno hlađenje jezgra NE "Krško" : magistrsko delo | |
Vertical stratification model in RELAP5 computer code | |
Vpliv zanesljivosti zunanjega električnega napajanja na varnost jedrske elektrarne | |
Vrednotenje nastavitev varovalnega sistema tlačnovodnega reaktorja | |
WAHALoads - two-phase flow water hammer transients and induced loads on materials and structures of nuclear power plants : WAHA3 code manual | |
When to use feed and bleed during small break LOCA | |
Začepitev cevi uparjalnikov v jedrski elektrarni in velika izlivna nezgoda | |
Zaključno poročilo o IJS pregledu NEK RELAP5/MOD2 baze podatkov NEK | |
Zaključno triletno poročilo projekta : Industrijski hazard | |
Zbirna strokovna ocena posegov in preizkusov NEK po remontu'89 |