In this field, using the Monte Carlo simulation softwares such as MCNP, GEANT4, PENELOPE, or self-writing codes to evaluate the characteristics of the spectrometer, calculate the radiation dose from sources of radionuclides, accelerators, nuclear reactors, equipments for medical diagnostic or radiation therapy, assess radiation safety, design radiometer system.
The relevant works are published as:
- Evaluation of dose distribution from a linear accelerator at Cho Ray Hospital by MCNP5,
- Optimal design for gamma scattering measurements by MCNP5,
- Assessment of shielding safety in diagnostic radiology room using MCNP5 code,
Study the effect of secondary scattering to the total efficiency by using MCNP code,
- Simulation for Leksell Gamma Knife radiosurgery device using MCNP5,
- Simulation for cyclotron accelerator at Cho Ray Hospital by MCNPX,
- Survey for matrix and density effects on peak efficiency of spectrometer with HPGe detector by MCNP code,
- Simulation for Shell Model by SMMC methods,
- Develop a program of simulating the full energy peak efficiency using the HPGe detector,
- Develop a program of simulating photon-electron transport by Monte Carlo method,
- Survey for the dose distribution in diagnostic radiology room using MCNP code,
- Study on the shielding material in diagnostic radiology room with MCNP code,
- Simulation of muon lifetime by Geant4 code,
- Design of cosmic background shielding using Geant4,
- Survey for the distribution of the scattering gamma using NaI(Tl) detector by Geant4 code.
- Study on the effect of non-linear response to the energy resolution of the plastic scintillation detector using Geant4.
