Institute of Nuclear Science and Technology

Reactor Physics and Engineering Division (RPED)

Phone: 880-2-7789819 Fax: 880-2-7701337
Email: inst@bangla.net

Head: Dr. Mafizur Rahman

Objectives

The safe and efficient planning and operation of nuclear reactors require a wide spectrum of reactor calculations. The program of the division is to conduct R&D using modern methods for the computation of nuclear reactors, with particular emphasis on reactor physics, design and safety. The ultimate objective of the division is to support the development of infrastructure for future nuclear power program to meet the increasing demand of electricity.

Activities

Development/management of Computer Codes for Reactor Engineering and Nuclear Data Processing.
To procure, implement and update computer codes related to reactor engineering and nuclear data processing. In this regard we maintain international collaboration with IAEA, ORNL, JAERI, KAERI and NEA Data Bank and contribute towards development of application oriented computer codes and nuclear data libraries.

Core Management of the TRIGA MARK-II research reactor at AERE, Savar

The study aims at establishing the applied technological know-how for in-core fuel management studies of the TRIGA MARK-II research reactor at AERE, Savar. This requires planning of strategies for fuel reshuffling and/or reloading schemes and its safe implementation. The TRIGA MARK-II research reactor was commissioned in late 1986 and benchmark neutronic analyses have been performed only for the fresh core using different computer codes WIMS-CITATION, SRAC and Monte Carlo code MCNP, MVP. The results obtained so far from the study have been incorporated in the Safety Analysis Report (SAR). Burn-up analysis has been performed using Monte Carlo code MVP and deterministic code SRAC. Steps have been taken to perform experimental measurement of fuel burnup of some particular fuels that will enable benchmarking of the calculation and eventually it will be possible to prepare a fuel management scheme to ensure the safe and economic use of the TRIGA core.
Development of Shielding Materials and Related Technolog
To develop shielding materials, prepare their data-bases, and to provide shield design for different radiation installations in the country. Two new shielding materials namely, Ilmenite-Magnetite (I-M) concrete and Poly-Boron have been developed with locally available materials for g and neutron shielding. I-M concrete is used for the TRIGA reactor shielding. The shield design for the Brachytherapy installation of Dhaka Medical College Hospital and isotope storage pits of industrial radiotherapy of BAEC have been provided
Reactor Thermal Hydraulic Analysis
To investigate the thermal hydraulic behavior of the 3 MW TRIGA MARK-II research reactor as well as power reactor both steady-state and transient conditions of reactor operation. Major thermal hydraulic parameters like DNBR, fuel temperature distribution, fuel surface heat flux and heat transfer coefficients, peak power and prompt energy release after pulse, accidental reactivity insertion have been studied. Loss-of-flow accident analyses conducted on the forced-flow-cooled TRIGA core have also been analyzed. Further studies are in progress using RELAP5 computer code. The results obtained so far from the study have been incorporated in SAR and will contribute to safe operation and better utilization of the reactor.
Fuel Cycle Analysis of Small and Medium Scale Power Reactors
For developing countries like Bangladesh, small and medium size nuclear power plants can play important role to supplement the power shortage. With this view in mind and to keep us abreast with the current state-of-the-art of power reactor technology, some studies have been initiated to analyze the fuel cycle of small and medium size nuclear power plants. To start with, a small PWR of 100 MW thermal power output having fuel assemblies of the type being used in current commercial PWR’s is being analyzed.
Academic activities
The division supports academic activities such as M.Sc., M.Phil, and Ph.D. programs in collaboration with different local universities.
Nuclear related services and products provides by RPED.
- Provides Shielding design for different nuclear radiation installations of the Country.
- Safety analysis of the irradiations/ experiments in the TRIGA MARK-II research reactor.

Achievements

Through continuous effort, the Reactor Physics and Engineering Division, INST has achieved some fruitful results in different fields of reactor physics and related technology of which a few are given below:

The detail neutronic and safety calculation results on TRIGA Mark-II research reactor at AERE, Savar have been incorporated in the Safety Analysis Report (SAR) in updating the same to IAEA standard.
A primary reshuffled core has been proposed as an important output of the research work on TRIGA reactor analysis.
Developed two shielding materials I-M concrete and Poly-boron (From locally available ingredients) for gamma and neutron shielding respectively. I-M concrete has been used for TRIGA reactor shielding.
Render services on ‘Shield-Design’ for the experimental facilities around TRIGA Mark-II research reactor as well as for different radiation installations in the country.
Academic programs (M.Sc. M.Phil, Ph.D.) are being carried out jointly with local universities under the active supervision of the scientists of the division.
Scientific papers have been published regularly in reputed journals of national and international origin.

Publications

Several national and international papers have been published on the research activities carried out in the division since its commencement. Some international publications are as follows:

M.M Sarker, S.I.Bhuiyan , S. Bosu , M.T. Chowdhury “A Comparative Study of WIMS Multigroup Crossection Data of Some Isotope Processed by the Code System NJOY’99” Progress in Nuclear Energy . Vol 49 Number 7, 2007.
M J H Khan, M Rahman, F U Ahmed, S I Bhuiyan, A Haque and A Zulquarnain, “Shield Design of Concrete Wall between Decay Tank Room and Primary Pump Room in TRIGA Facility”, Journal of Radiation Protection, ROK, December 2007.
M. Rahman, T. Suzaki, T. Mori, M.A.W. Mondal and Badrul Alam, “Validation Study of the Monte Carlo Code MVP for Analysis of Two-Region TCA Critical Experiments with PWR-type MOX Fuels”, Progress Nucl. Energy, 48, pp. 703-726, 2006.
M. Rahman, M.A.W. Mondal, Badrul Alam, “Validation Study of the Cell Code WIMS-D and a 69 group library based on JENDL-3.2”, Annals of Nuclear Energy, 31(2004): 1357-1383, 2004.
M.Q. Huda, M. Rahman, M.M. Sarker and S.I. Bhuiyan; “Benchmark Analysis of the 3 MW TRIGA Mark-II Research Reactor using Monte Carlo Techniques”, Annals of Nuclear Energy, 31(11), p 1299, UK, December 2004.
M. Q. Huda and M. Rahman, “Thermo-hydrodynamic and Safety Parameter Studies of the TRIGA MARK-II Research Reactor”, Annals of Nuclear Energy, 31(10):1101-1118, 2004.

Resource Person

Name	Designation	Qualification	Specialization
Dr. Mafizur Rahman	Chief Scientific Officer	Ph.D.	Reactor Engineering
Dr. Md. Muslehuddin Sarker	Chief Scientific Officer	Ph.D.	Reactor Engineering
Jahirul Haque Khan	Senior Scientific Officer	M.Sc.	Reactor Physics
Mohammad Sayem Mahmood	Senior Scientific Officer	M.Sc.	Reactor Physics
Dr. Badrun Nahar Hamid	Senior Scientific Officer	Ph.D.	Reactor Physics
Mohammad Abdul Motalab	Scientific Officer	M.Sc.	Reactor Physics
SobrobJoti Bosu	Scientific Officer	M.Sc.	Reactor Physics
Mohammed Tareque Chowdhury	Scientific Officer	M.Sc.	Reactor Physics