MAKING OF Ba-133 STANDARD SOURCE AS SIMULATOR I-131Hermawan Candra, Pujadi, Gatot WurdiyantoPTKMR � BATANABSTRACTMAKING OF Ba-133 STANDARD SOURCE AS SIMULATOR I-131. One of nuclear instrumentation at nuclear medicine is Dose Calibrator. This equipments represent
Tuesday, February 22, 2011
Wednesday, February 16, 2011
Standardisasi Sumber Radioaktif Bentuk Gas Argon-41 Menggunakan Metode Spektrometri Gamma
STANDARDISASI SUMBER RADIOAKTIF BENTUK GAS ARGON-41 MENGGUNAKAN METODE SPEKTROMETRI GAMMAGatot Wurdiyanto, Hermawan Candra & PujadiPTKMR - BATANABSTRAKTelah dilakukan standardisasi sumber radioaktif berbentuk gas argon-41 di Pusat Teknologi Keselamatan dan Metrologi Radiasi � Badan Tenaga
Labels:
aktivasi neutron,
Argon-41,
spektrometri,
standardisasi
Sunday, February 13, 2011
Core Modeling For The Analysis On Multiplication Constant Calculation Of HTR-Proteus Reactor
CORE MODELING FOR THE ANALYSIS ON MULTIPLICATION CONSTANT CALCULATION OF HTR-PROTEUS REACTORZuhair, Suwoto, Ign. Djoko IriantoPTRKN � BATANABSTRACTCORE MODELING FOR THE ANALYSIS ON MULTIPLICATION CONSTANT CALCULATION OF HTR-PROTEUS REACTOR. PTRKN as a working unit
Wednesday, February 9, 2011
Determination Of The Counting Optimal Distance Radiation Detector Of The Air Monitor
DETERMINATION OF THE COUNTING OPTIMAL DISTANCE RADIATION DETECTOR OF THE AIR MONITORHolnisar, Hermawan Candra & Gatot WurdiyantoABSTRACTDETERMINATION OF THE COUNTING OPTIMAL DISTANCE RADIATION DETECTOR OF THE AIR MONITOR. Determination of the optimal distance for
Sunday, February 6, 2011
Application Of Radiation Protection On Irradiated Materials, Ar-41, At G.A. Siwabessy Reactor
APPLICATION OF RADIATION PROTECTION ON IRRADIATED MATERIALS, Ar-41, AT G.A. SIWABESSY REACTORWijono dan Gatot WurdiyantoPTKMR-BATANABSTRACTAPPLICATION OF RADIATION PROTECTION ON IRRADIATED MATERIALS, Ar-41, AT G.A. SIWABESSY REACTOR. The application of radiation protection on irradiated materials,
Thursday, February 3, 2011
Neutron And Gamma Dose Modeling In The Triga 2000 Reactor Using Monte Carlo Method MCNP5.
NEUTRON AND GAMMA DOSE MODELING IN THE TRIGA 2000 REACTOR USING MONTE CARLO METHOD MCNP5.Rasito1, P. Ilham Y. dan Putu SukmabuanaPusat Teknologi Nuklir Bahan dan Radiometri � BATANABSTRACTNEUTRON AND GAMMA DOSE MODELING IN THE
Labels:
gamma and neutron dose,
MCNP5,
TRIGA 2000 reactor