Prošek, Andrej
Prošek, Andrej 1962-
Prosek, A
Andrej Prošek slovenski fizik
VIAF ID: 121234683 ( Personal )
Permalink: http://viaf.org/viaf/121234683
Preferred Forms
- 100 0 _ ‡a Andrej Prošek ‡c slovenski fizik
- 100 1 _ ‡a Prosek, A
- 100 1 _ ‡a Prošek, Andrej, ‡d 1962-
- 100 1 _ ‡a Prošek, Andrej
-
- 100 1 _ ‡a Prošek, Andrej ‡d 1962-
4xx's: Alternate Name Forms (11)
Works
Title | Sources |
---|---|
Accuracy quantification of BETHSY 9.1B test | |
Estimation of operator action time windows by RELAP/MOD3.3, 2009: | |
Izjava za ponovno obratovanje NE Krško po remontu 2004 in menjavi goriva po zaključenem 20. gorivnem ciklu v NE Krško | |
LOCAs with loss of one active emergency cooling system simulated by RELAP5 | |
Loss of external load analysis with RELAP5/MOD3.3 patch 03 code | |
Methodology for selecting initiating events and hazards for consideration in an extended PSA | |
Nuclear Option in Countries with Small and Medium Electricity Grids | |
Ocena negotovosti realističnih simulacij potekov nezgod v jedrskih elektrarnah : disertacija | |
Proceedings | |
Quantitative code assessment with improved FFTBM by signal mirroring | |
Reactor Excursion and Leak Analysis Program 5 analysis of mitigation strategy for extended blackout power condition in Pressurized Water Reactor | |
Reactor trip analysis at Krško NPP | |
Relap5 and TRACE calculations with quantitative assessment against Achillles natural reflood experiment | |
RELAP5/MOD3.3 analyses of core heatup prevention strategy during extended station blackout in PWR | |
RELAP5/MOD3.3 code validation with plant abnormal event : [selected papers from the International Conference Nuclear Energy for New Europe 2007, September 10-13, Portorož, Slovenia] | |
RELAP5/MOD3.3 transient analysis of loss of normal feedwater (LOFW) for Krško full scope simulator (KFSS) ANSI/ANS annual verification | |
RELAP5 simulation of design extension condition with loss of all feedwater in PWR | |
RELAP5 to TRACE input model conversion procedure and advanced post processing of the results for the ISP-25 test | |
Report on the technical co-operation project RER/9/004 on the evaluation of safety aspects of WWER-440 model 213 nuclear power plants : Simulation of a beyond design basis accident with bleed and fleed preventive measures | |
Response surface generation with optimal statistical estimator | |
Response surface use in safety analyses | |
Review of design extension conditions experiments and analyses for non-degraded core | |
Safety margin evaluation methods. | |
Safety margins of operating reactors : analysis of uncertainties and implications for decision making : [presented at Technical Committee Meeting on Safety Margins of Operating Reactors and Implications for Decision Making including Considerations of Uncertainties of Analysis, 15-19 October 2001, Vienna] | |
Semiscale S-NC-02 and S-NC-03 natural circulation tests performed by RELAP5/MOD3.3 Patch05 | |
Simulacije projektnih nezgod za verifikacijo popolnega simulatorja NE Krško | |
Simulation of containment response during a large-break loss-of-coolant accident scenario with the CONTAIN computer code | |
Simulation of hypothetical small-break loss-of-coolant accident in modernized nuclear power plant | |
Simulation of L9-1/L3-3 experiment w ith multiple failures on LOFT facility | |
Simulation of ROSA/LSTF test SB-HL-02 using RELAP5 and TRACE | |
Specialised training course "Setting up a management system" : deliverable D 3.4 : facilitation guide WP3 : reporting period 1st May 2012 - 31st October 2013 | |
Spent fuel pit heatup and evaporation critical review of the report NEK ESD-TR-07/11 | |
Spent fuel storage system management for a typical two loop PWR nuclear power plant during hypothetical complete loss of external cooling | |
Srečanje CAMP v Ljubljani | |
Statement gor Krško NPP anew operationafter regular outage and refuelling at the end of fuel cycle 18 | |
Statistic method used for LB LOCA PCT calculation | |
Status of CAMP Activities in Slovenia | |
Strokovna ocena analize 24% začepljenosti cevi uparjalnikov NE Krško : ustreza programu zagotovitve kakovosti | |
Strokovna ocena znižanja koncentracije bora v BIT-u : strokovna ocena | |
Strokovno mnenje pooblaščenega izvedenca za sevalno in jedrsko varnost strokovna ocena remontnih del, posegov in preskusov v med zaustavitvijo NUKLEARNE ELEKTRARNE KRSKO zaradi menjave goriva ob koncu 26. gorivnega cikla | |
Strokovno mnenje za mod.432-AS-L "Zamenjava centralnega alarmnega sistema" | |
Strokovno mnenje za poročilo "NEK Periodic Safety Review-Summary Report" | |
Strokovno mnenje za spremembo USAR in NEK-TS po predlogi "Replacement of the DEH turbine control system, turbine emergency trip control system and MRS control" | |
Theory of the best estimate plus uncertainty methods | |
Thermal-hydraulic safety analyses supporting the steam generator replacement and uprating at Krško nuclear power plant | |
A tool for drawing with Excel | |
TRACE code analysis of a two-loop PWR coolant mixing in the reactor pressure vessel | |
Uncertainty evaluation of CFD simulation using optimal statistical estimator [Elektronski vir] | |
Uncertainty evaluation of reactor safety parameters during SB LOCA | |
Uporaba realistične metodologije za preračun velike izlivne nezgode v jedrski elektrarni : magistrsko delo | |
Use of fast Fourier transform for sensitivity analysis | |
User effect on the IAEA-SPE-4 calculation | |
Uvajanje statističnih metod v termohidravlične analize jedrskih elektrarn | |
Validation of two-fluid boiling flow model on the DEBORA benchmark experimental data | |
Vloga Termoelektrarne Brestanica pri zagotavljanju varnosti jedrske elektrarne v Krškem | |
Vpliv delovanja reaktorske črpalke med izlivno nezgodo | |
When to use feed and bleed during small break LOCA | |
WP3: Integration and safety analysis : Del 3.11 - Constraining the uncertainties in the components modelling (causes and consequences) - application to Station Blackout event : peer-reviewed report | |
Zaključno poročilo o IJS pregledu NEK RELAP5/MOD2 baze podatkov NEK | |
Zbirna strokovna ocena posegov in preizkusov NEK po remontu'89 |