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
Thursday, November 25, 2010
Numerical Assesment Of Characteristic Passive Cooling System With Air At Containment AP1000 Model
NUMERICAL ASSESSMENT OF CHARACTERISTIC PASSIVE COOLING SYSTEM WITH AIR AT CONTAINMENT AP1000 MODELWidi Laksmono1), Ari Darmawan Pasek1), Efrizon Umar2)1)Fakultas Teknik Mesin dan Dirgantara � ITB2)Pusat Teknologi Nuklir Bahan dan Radiometri � BATANABSTRACTNUMERICAL ASSESSMENT OF
Friday, November 5, 2010
Analysis Of Void Percentage Impact On Neutronic And Thermohydraulic Condition Of Boiling Water Reactor
ANALYSIS OF VOID PERCENTAGE IMPACT ON NEUTRONIC AND TERMOHYDRAULIC CONDITION OF BOILING WATER REACTORNanang Triagung Edi Hermawan dan Catur Febriyanto SutopoProgram Magister Rekayasa Energi Nuklir � Institut Teknologi BandungABSTRACTANALYSIS OF VOID PERCENTAGE IMPACT ON
Sunday, October 31, 2010
Verification Of Thermal-Hydraulic Design Of PWR Core 1000 MWe Class
VERIFICATION OF THERMAL-HYDRAULIC DESIGN OF PWR CORE 1000 MWe CLASS.Muh. Darwis Isnaini dan Pudjijanto MSPTRKN � BATAN, Kawasan Puspiptek Gd.80 Serpong, Tangerang, 15310ABSTRACTVERIFICATION OF THERMAL-HYDRAULIC DESIGN OF PWR CORE 1000 MWe CLASS. Verification of
Tuesday, October 19, 2010
Evaluation and Analysis of Cooling Study of High Temperature Heated Rod on Queen-II Test Section for Bottom Reflooding Procces experiments
EVALUATION AND ANALYSIS OF COOLING STUDY OF HIGH TEMPERATURE HEATED ROD ON QUEEN-II TEST SECTION FOR BOTTOM REFLOODING PROCESS EXPERIMENTS.Puradwi I.W., M. Juarsa, Hendro Tj.Pusat Teknologi Reaktor dan Keselamatan Nuklir - BATANKawasan PUSPIPTEK Gedung
Wednesday, October 13, 2010
Analysis Of Helium Gas Flow Through Turbine Nozzle For Molten Salt Power Reactor
ANALYSIS OF HELIUM GAS FLOW THROUGH TURBINE NOZZLE FOR MOLTEN SALT POWER REACTORSri SudadiyoPTRKN-BATAN, Kawasan PUSPIPTEK Gd. 80, Serpong, Tangerang, 15310ABSTRACTANALYSIS OF HELIUM GAS FLOW THROUGH TURBINE NOZZLE FOR MOLTEN SALT POWER REACTOR. From
Thursday, October 7, 2010
India Safeguards Agreement: Is Nuclear Non-Proliferation Regime Strengthening?
INDIA SAFEGUARDS AGREEMENT: IS NUCLEAR NON-PROLIFERATION REGIME STRENGTHENING?Eri HiswaraPusat Teknologi Keselamatan dan Metrologi Radiasi � BATANKawasan Nuklir Pasar Jumat, Jl. Cinere Pasar Jumat, Jakarta 10270ABSTRACTINDIA SAFEGUARDS AGREEMENT: IS NUCLEAR NON-PROLIFERATION REGIME STRENGTHENING? The August
Sunday, October 3, 2010
Study On Reactor Trip Systems Performance Of EPR 1600
STUDY ON REACTOR TRIP SYSTEMS PERFORMANCE OF EPR 1600Nafi Feridian, YuliastutiPusat Pengembangan Energi Nuklir (PPEN) - BATANJl. Mampang Prapatan, Kuningan Barat, JakartaABSTRACTSTUDY ON REACTOR TRIP SYSTEMS PERFORMANCE OF EPR 1600. The study on reactor
Wednesday, September 29, 2010
The Probabilistic Analysis Of Power Reactor Radiation Safety At LOCA (Loss Of Coolant Accident) Condition
THE PROBABILISTIC ANALYSIS OF POWER REACTOR RADIATION SAFETY AT LOCA (LOSS OF COOLANT ACCIDENT) CONDITIONPande Made UdiyaniPusat Teknologi Reaktor dan Keselamatan Nuklir - BATANPTRKN-BATAN, Kawasan PUSPIPTEK Gd.80, Serpong, Tangerang, 15310ABSTRACTTHE PROBABILISTIC ANALYSIS OF POWER
