ASSESSMENT OF DIFFUSION GAMMA AND NEUTRON DOSE, FOR THE PURPOSE OF OPTIMIZING THE RADIATION PROTECTION IN TRIGA 2000 BATAN
The TRIGA 2000, located in Bandung Indonesia, is a research reactor installation which is currently operated at 1000 kW. As it is a nuclear installation, Gamma and neutron radiation exposure will contribute to occupational doses that will be received by operators and other radiation workers. To m...
Saved in:
| Main Author: | |
|---|---|
| Format: | Theses |
| Language: | Indonesia |
| Subjects: | |
| Online Access: | https://digilib.itb.ac.id/gdl/view/41841 |
| Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
| Institution: | Institut Teknologi Bandung |
| Language: | Indonesia |
| Summary: | The TRIGA 2000, located in Bandung Indonesia, is a research reactor installation which is
currently operated at 1000 kW. As it is a nuclear installation, Gamma and neutron radiation
exposure will contribute to occupational doses that will be received by operators and other
radiation workers. To maintain the safety of radiation workers, assessment of gamma and
neutron radiation is needed in the TRIGA 2000 reactor. A survey was carried out in the hall
reactor using the RTD 30 and RadEye NL detectors to measure the gamma and neutron dose
rate during the operation of the reactor area which is divided in 32 points. In addition to the
direct measurement, calculations has been realized with simulation data dose using Monte
Carlo MCNPX and PHITS to get the output of the dose in a limited distance and followed by
the extrapolation using the TVL methods to complete the calculation of the dose rate. The study
will focus on the assessment of the diffusion Gamma and neutron doses by doing the
measurement and simulation data collect for the aim of the optimization of the Radiation
protection policy in the reactor TRIGA 2000 Bandung. The results of the measurement are
shown with graph in different power and the simulations are illustrate by graphical distribution
dose of gamma and neutron using PHITS code output and extrapolation using TVL method to
estimate the hall reactor dose. All simulation graph are designed using ANGEL software. The
results from simulations will be compared with several points chosen from the 32 points of
mapping area. A preventive technique to mitigate the exposure of the worker and publics is
elaborated to optimize the Radiation protection program and suggestions are given regarding
to the measurement and the simulation. |
|---|