THERMAL PARAMETER TRANSIENT ANALYSIS OF DROPLETS IN NUCLEAR POWER PLANT COOLING TOWERHendro Tjahjono Pusat Teknologi Reaktor dan Keselamatan Nuklir BATANABSTRACT THERMAL PARAMETER TRANSIENT ANALYSIS OF DROPLETS IN NUCLEAR POWER PLANT COOLING TOWER. In Nuclear
Friday, December 31, 2010
Thursday, December 23, 2010
Safety Evaluation Of Reactor Core For PWR Based On Initiating Event And Design Aspect
SAFETY EVALUATION OF REACTOR CORE FOR PWR BASED ON INITIATING EVENT AND DESIGN ASPECTD. T. Sony TjahyaniPTRKN - BATANABSTRACTSAFETY EVALUATION OF REACTOR CORE FOR PWR BASED ON INITIATING EVENT AND DESIGN ASPECT. Safety evaluation
Sunday, December 19, 2010
Analysis On Early Phase Of Severe Accident In Nuclear Power Plant
ANALYSIS ON EARLY PHASE OF SEVERE ACCIDENT IN NUCLEAR POWER PLANTSugiyantoPTRKN - BATANABSTRACTANALYSIS ON EARLY PHASE OF SEVERE ACCIDENT IN NUCLEAR POWER PLANT. Analysis on early phase (during100 minutes after accident initiated) of severe
Thursday, December 16, 2010
Multiobjective Simulated Annealing Method Implementation For Pwr Fuel Loading Pattern Optimization Using Corebn Code
MULTIOBJECTIVE SIMULATED ANNEALING METHOD IMPLEMENTATION FOR PWR FUEL LOADING PATTERN OPTIMIZATION USING COREBN CODEChristina Novila Soewono, Alexander Agung, Sihana Jurusan Teknik Fisika Fakultas Teknik - Universitas Gadjah MadaABSTRACT MULTIOBJECTIVE SIMULATED ANNEALING METHOD IMPLEMENTATION FOR
Thursday, December 9, 2010
Implementation Of Genetic Algorithm Method For PWR Fuel Loading Pattern Optimization Using COREBN Code
IMPLEMENTATION OF GENETIC ALGORITHM METHOD FOR PWR FUEL LOADING PATTERN OPTIMIZATION USING COREBN CODEPetrus, Alexander Agung, SihanaJurusan Teknik Fisika, Fakultas Teknik, Universitas Gadjah MadaABSTRACTIMPLEMENTATION OF GENETIC ALGORITHM METHOD FOR PWR FUEL LOADING PATTERN OPTIMIZATION
Tuesday, December 7, 2010
Analysis Fuel Burn-Up Distribution Of 1000 MWe PWR-NPP Core Fuelled By UO2 3,4 Wt%.
ANALYSIS FUEL BURN-UP DISTRIBUTION OF 1000 MWE PWR-NPP CORE FUELLED BY UO2 3,4 WT%.Jati Susilo1, Tukiran Surbakti2, Iman Kuntoro31,2Pusat Teknologi Reaktor Dan Keselamatan Nuklir (PTRKN)3Pusat Teknologi Bahan Industri NuklirABSTRACTANALYSIS FUEL BURN-UP DISTRIBUTION OF 1000
Thursday, December 2, 2010
Analysis Of The Temperature Coefficient Of The Pwr 1000 MWe Fuel Assembly Of Enrichment Function Using MCNP Code
ANALYSIS OF THE TEMPERATURE COEFFICIENT OF THE PWR 1000 MWe FUEL ASSEMBLY OF ENRICHMENT FUNCTION USING MCNP CODERokhmadi dan TukiranPUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR-BATANKawasan PUSPIPTEK Gd. No. 80 Serpong 15310ABSTRACTANALYSIS OF THE TEMPERATURE
Wednesday, December 1, 2010
Studi Perhitungan Reaktor HTR Pebble-Bed Dengan Berbagai Opsi Desain Matriks Bahan Bakar
STUDI PERHITUNGAN REAKTOR HTR PEBBLE-BED DENGANBERBAGAI OPSI DESAIN MATRIKS BAHAN BAKARZuhair dan SuwotoPusat Teknologi Reaktor dan Keselamatan Nuklir � BATANABSTRACTSTUDY ON PEBBLE-BED HTR REACTOR CALCULATION WITH SEVERAL OPTIONS OF FUEL MATRIX DESIGNS. Pebble-bed HTR
