Institute of Nuclear Science and Technology

Reactor Physics and Engineering Division (RPED)

Phone: 880-2-7790683 Fax: 880-2-8130102,880-2-7789337
Email: jahirulkhan@yahoo.com

Head: Md. Jahirul Haque Khan

    Objectives:

• Reactor Physics Study of Nuclear Reactors using Sophisticated Computer Codes.
• Computational and Experimental Thermal Hydraulic Study of Nuclear Reactors.
• Computational Attenuation Property Study of Materials for Development of Radiation Shielding Materials.
• Measurement of Fatigue and Fracture of the Structural Components for Research Reactor.
• Measurement of Stress and Vibration analysis of Pumps, Motors, Exi-check Valves and Primary Piping systems of TRIGA Research Reactor.
• The ultimate objective of the division is to support the development of national infrastructure for nuclear power programs to meet up increasing demand of electricity in the country.

   Major Facilities:

1. Sophisticated reactor engineering computer codes installed in PC
2. Measuring Equipment/Instruments
3. Thermal Hydraulic Rig
4. Material Testing Machine
5. Stress & Vibration Measuring/Analysis Facilities

    Group Members:

    Research Activities:

The safe and efficient planning of nuclear reactor operation needs a wide spectrum of reactor engineering calculations. The program of the division is to conduct R & D activities using modern methods for the computational analysis of nuclear reactors, with particular emphasis on reactor physics, design and safety. The division procures and implements computer codes related to reactor engineering and nuclear data processing. The activities of the division are conducted under the following research projects:

• Reactor Engineering and Nuclear Data Processing
  Objective: Development of computational facility for reactor engineering and nuclear data processing.
  Status: The computer codes SRAC, WIMSD-5B, MCNP4C and MVP are in active use for the Neutronics calculations. MCNP4C along with Micro-Shield-5.0 are in use for shielding studies. Also RELAP5, EUREKA-2/RR and COOLOD-N2 have been successfully implemented for thermal hydraulics and transient analysis.
• Reactor Analysis and Reactor Design
  Objective: Core Management of TRIGA Mark-II Research Reactor
  Status: For efficient, safe and economic utilization of TRIGA reactor, in-core fuel management study is going on. Present core burn-up life of the reactor has been calculated. Tentative reshuffled core with new irradiation channels has been proposed for increased isotope production.
• Heat Transfer and Thermal Hydraulics Studies
  Objective: Heat transfer and thermal hydraulics studies of nuclear reactors.
  Status: Some preliminary thermal hydraulics and transient analysis have been performed with two new computer codes EUREKA-2/RR and COOLOD-N2. Research reactor safety calculation experience using those codes has been shared among the FNCA countries.
• Materials Strength Studies
  Objective: Establishment and use of computational and experimental facilities for vibration, stress and fracture analysis of nuclear reactor system
  Status: Under planning.
• Radiation Shielding Technology
  Objective: Developments of shielding materials and related technology.
  Status: Development of radiation shielding materials locally against gamma & neutron radiation and their attenuation property studies are going on.
• International Projects
  IAEA Coordinated Research Project (CRP1496):
  
  Seventeen countries including Bangladesh are participating the IAEA coordinated research project entitled, "Innovative methods in research reactor analysis: Benchmark against experimental data on neutronics and thermalhydraulic computational methods and tools for operation and safety analysis of research reactors", (CRP 1496). Under this project some of the neutronics experimental benchmark problem of SPERT-IV D-12/25 has been simulated using the Monte Carlo code MVP. The confirmed calculation method through this benchmark will be applied for neutronic analysis of TRIGA.
  Forum for Nuclear Cooperation in Asia (FNCA):
  
  Safety analysis knowledge of research reactors has been shared among the member countries of the "Forum for Nuclear Cooperation in Asian" under the project entitled, "Research Reactor Utilization - Research Reactor Technology project" by using common codes COOLOD-N2 and EUREKA2/RR. Applying the shared knowledge the safety analysis of TRIGA reactor has been improved.

    Academic Activities:

The division plays an important role to perform academic research activities. In collaboration with different national universities Ph.D. and M.Sc students are conducting their research work under supervision of the scientists of the division. Services: Shield designs are provided from the radiation shielding point of view using the standard computer codes for different types of radiation installations or facilities in the country including Bangladesh Atomic Energy Commission.

    Achievements:

Through continuous effort, the division has achieved some fruitful results in different fields of reactor physics and related technology. The results obtained so far from the neutronics and thermal hydraulics studies for the TRIGA Mark-II research reactor have been incorporated in the Safety Analysis Report (SAR). Reconfigured core has been proposed for increased isotope production, as an important output of the research work. Two shielding materials namely, Ilmenite-Magnetite (I-M) concrete and Poly-Boron have been developed with locally available materials for gama and neutron shielding respectively. The shield designs for the Brachytherapy Installation of Dhaka Medical College Hospital, Isotope Storage Pits of Industrial Radiotherapy and Neutron Radiography Facility of TRIGA Reactor of BAEC have been provided. Several researchers of different universities have completed their Ph.D. and M.Sc. research from this laboratory. A number of scientific papers are published in the reputed local and international journals.

    List of Publications:

1. S.I. Bhuiyan, M.A.W. Mondal, M.M. Sarker, M. Rahman, M.S. Shadatullah, M.Q. Huda, T.K. Chakrobortty, and M.J.H. Khan, "Criticality and Safety Parameter Studies of a 3-MW TRIGA Mark-II Research Reactor and Validation of the Generated Cross-Section Library and Computational Method", An International Journal of the ANS, Nuclear Technology, ISSN: 0029-5450, Vol. 130, No.2, May 2000, USA.
2. M.J.H. Khan, R.U. Miah, S.M. Hossain, M. Rahman and M.A. Awal, "Neutron Activation Cross-Section for the 76Ge (n,2n)75Ge Process in the Energy Range 13.82-14.71 MeV", Jahangirnagar University Journal of Science, ISSN 1022-8594, Vol. 22 & 23, 217-227, September 2000.
3. M.M. Sarker, M.J.H. Khan, S.I. Bhuiyan and M.A.W. Mondal, "Validation of Generated Four Group Cross-Section Library for TRIGA LEU Fuel and Benchmarking Some Experimental and Operational Data", Jahangirnagar University Journal of Science, ISSN 1022-8594, Vol. 22 & 23, 229-243, September 2000.
4. Z. Ahmed, M.J.H. Khan, S.I. Bhuiyan and M.A.W. Mondal, "Optimization of Radiation Shielding Design for Brachytherapy Facility at Dhaka Medical College Hospital", Jahangirnagar University Journal of Science, ISSN 1022-8594, Vol. 24, 121-129, December 2000.
5. M.J. H. Khan and M.M. Sarker, "Investigations of Integral Parameters for TRX and BAPL Benchmark Lattices of Thermal Reactor with WIMSD Code," Jahangirnagar University Journal of Science, ISSN 1022-8594, Vol. 25, December 2002.
6. M.J.H. Khan, M.Q. Huda, A.S. Mollah, F.U. Ahmed, M.M. Sarker and S.I. Bhuiyan, "Shield Design for the Brachytherapy Facility at Dhaka Medical College Hospital," Bangladesh Journal of Medical Physics, ISSN: 1727-6179, Vol. 3, January 2004.
7. M.J.H. Khan, M.M. Sarker, M. Rahman and S.I. Bhuiyan, "Comparative Studies of IAEA Benchmark Lattices with WIMSD & SRAC Code Systems for WLUP", Jahangirnagar University Journal of Science, ISSN 1022-8594, Vol. 29, 33-43, December 2006.
8. M.J.H. Khan, one of the Participants and Contributors in IAEA supported CRP for "WIMS-D LIBRARY UPDATE: Final Report of a Coordinated Research Project", a Book for IAEA Library, ISBN 92-0-105006-2, STI/PUB/1264, Vienna, Austria, May 2007.
9. S. Hossain, M.J.H. Khan, M.M. Sarker, M.N. Uddin, S.M.A. Islam and M.H. Ahsan, "Generation of 69 Group Cross Section Library from CENDL Data for Lattice Code WIMS and Benchmarking through TRX & BAPL Lattices of Thermal Reactors", Jahangirnagar University Journal of Science, ISSN 1022-8594, Vol. 30, No. 2, 107-113, December 2007.
10. 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, The Korean Association for Radiation Protection, ISSN 0253-4231, Vol. 32, No 4, December 2007, Korea.
11. M.J.H. Khan, M. Shamsuzzaman, M.S. Rahman, and A.F.M. Rahman, "A Comparative Study on Determination of Exposure Rate in Air between the Micro-Shield Code and the Secondary Standard Dosimetry System", Journal of The Department of Physics, Jahangirnagar Physics Studies, ISSN 1999-6632, Volume 13, 2007.
12. S.M.T. Islam, M.M. Sarker, M.J.H. Khan, and S.M.A. Islam, "A Comparative Study of Integral Parameters for TRX and BAPL Benchmark Lattices of Thermal Reactors Using the Cross Section Library Generated from JENDL and JEF Evaluated Data Files", Progress in Nuclear Energy, ISSN 0149-1970, Volume 51, Number 2, March 2009, UK.
13. M.N. Uddin, M.J.H. Khan, M.M. Sarker and S.M.A. Islam, "Analysis of Integral Parameters using Two Models for CENDL-2.2 Evaluated Nuclear Data File and Their Benchmarking through TRX and BAPL Lattices of Thermal Reactors", Journal of the Department of Physics, Jahangirnagar Physics Studies, ISSN 1999-6632, Volume , June 2009.
14. M.N. Uddin, M.M. Sarker, M.J.H. Khan and S.M.A. Islam, "Validation of CENDL and JEFF Evaluated Nuclear Data Files for TRIGA Calculations through the Analysis of Integral Parameters of TRX and BAPL Benchmark Lattices of Thermal Reactors", Annals of Nuclear Energy, ISSN 0306-4549, Volume 36, Number 10, PP 1521-1526, October 2009, USA.
15. M.N. Uddin, M.M. Sarker, M. J. H. Khan and S.M.A. Islam, "Computational Analysis of Neutronic Parameters for TRIGA Mark-II Research Reactor using Evaluated Nuclear Data Libraries", Annals of Nuclear Energy, ISSN 0306-4549, Volume 37, Issue 3, March 2010, USA.
16. S.I. Bhuiyan, A.S. Mollah, F.U. Ahmed, M.A.W. Mondal, M.Q. Huda, M.J. H. Khan, M.A. Hossain and M.M. Hoque, "Shield Design Aspects for Installation of a Brachytherapy Facility at Dhaka Medical College Hospital", Presented and Published as Full Paper, Proceedings of the 1998 ANS Radiation Protection and Shielding Division Topical Conference, Technologies for the New Century, Vol. 2, April 19-23, 1998, USA.
17. S.I. Bhuiyan, M.M. Sarker, T.K. Chakroboetty, M.J.H. Khan and T. Kulikowska, "Evaluation of Significance of Zr Bound in ZrHx for its Possible Inclusion in the WIMSD-5 Cross-Section Library", Presented and Published as Full Paper, Proceedings of the 2000 Symposium on Nuclear Data, JAERI-Conf 2001-006, INDC(JPN)-188/U, March 2001, Japan.
18. M.M. Sarker, T.K. Chakrobortty, M.Q. Huda, M.J.H. Khan and M.S. Mahmud, "Utilization and Core management of the 3 MW TRIGA Mark-II RR at AERE, Savar", Proceedings of the IAEA/RCA Regional Workshop/Training Course on Core Management for Improved Utilization of Research Reactors, KAERI/NTC/IN/02-04, C7-RAS-4.020-003, May 13-24, 2002, Daejeon, Korea.
19. M.Q. Huda, T.K. Chakrobortty, M.J.H. Khan and M.M. Sarker, "Benchmark Tests of JENDL-3.3 and ENDF/B-VI Data Files Using Monte Carlo Simulation of the 3 MW TRIGA Mark-II RR", Proceedings of the International 2002 Symposium on Nuclear Data, JAERI Tokai, November 21-22, 2002.
20. M.J.H. Khan, M.M. Sarker, M. Rahman, M.Q. Huda, S. Bosu, M.S. Mahmood and S.I. Bhuiyan, "Benchmark Neutronic Analysis of the 3 MW TRIGA Mark-II Research Reactor Using Diffusion Theory Technique", Proceedings of the IAEA/RCA Regional Training Course on Research Reactor Neutronic Calculations, KAERI/GP-251/2006, 3-14 July 2006, Daejeon, Korea.
21. M.Q. Huda, M. Rahman, M.M. Sarker, M.J.H. Khan, M.S. Mahmood, S. Bosu and S.I. Bhuiyan, "Neutronic and Safety Parameter Studies of the 3 MW TRIGA Mark-II Research Reactor Using Monte Carlo Technique", Proceedings of the IAEA/RCA Regional Training Course on Research Reactor Neutronic Calculations, KAERI/GP-251/2006, 3-14 July 2006, Daejeon, Korea.
22. S.I. Bhuiyan, M.M. Sarker, M.S. Shadatullah, M.J.H. Khan and J.E. White, "A 69 Group WIMS Library Based on ENDF/B-VI Data for TRIGA Reactor Calculations and Its Analysis for TRX and BAPL Benchmarks". INST-66/RPED-19, December 1997.
23. S.I. Bhuiyan, M.A.W. Mondal, M. Rahman, M.M. Sarker, M.Q. Huda, M.S. Shadatullah, T.K. Chakroborty and M.J.H. Khan, "Core Analysis for Upgrading the 3 MW TRIGA Mark-II Research Reactor to Higher Flux". INST Report, INST-67/TRPSPD-I, December 1998.
24. S.I. Bhuiyan, M.M. Sarker, M. Rahman, T.K. Chakroborty, M.J.H. Khan and M.A. W. Mondal, "Comparative Studies of TCA Benchmarks with WIMSD and SRAC Code Systems for WIMSD Library Update Project", INST Report, INST-78/TRPSPD-6, November 2000.
25. M.J.H. Khan, M.Q. Huda and F.U. Ahmed. "Primary Shield Design Aspects for the Installation of a Brachytherapy Facility at Dhaka Medical College Hospital", INST Report, INST-79/TRPSPD-7, June 2001.
26. M.J.H. Khan, M.Q. Huda and F.U. Ahmed. "Optimized Shield Design Aspects for the Installation of a Brachytherapy Facility at Dhaka Medical College Hospital", INST Report, INST-80/TRPSPD-8, June 2001.
27. M.Q. Huda, M. Rahman, M.M. Sarker, M.J.H. Khan, M.S. Mahmood, N.H. Badrun, M.A. Motaleb and T. Chowdhury, "Validation of JENDL-3.3 and ENDF/B-VI Data Libraries Using Monte Carlo Simulation of TRIGA Reactor", Internal Report, INST-112/RPED-24, August 2007.
28. M. Rahman, M.S. Mahmood, M.T. Chowdhury, S. Basu, M.A. Motalab, M.M. Sarker, M.Q. Huda and M.J.H. Khan, "Evaluation of the MVP Model Developed for the TRIGA Mark-II Research Reactor at AERE, Savar, through Criticality and Reactivity analysis", Internal Report, INST-113/RPED-25, September 2007.
29. M. Rahman, M.T. Chowdhury, S. Basu, M.M. Sarker, M.Q. Huda, M.J.H. Khan, M.S. Mahmood, M.A. Motalab and N.H. Badrun, "Safety Calculation of TeO2 Irradiation in DCT of TRIGA Mark-II research Reactor at AERE, Savar, Using One Dimensional Heat Transfer Code GENGTC", Internal Report, INST-114/RPED-26, March 2008.
30. M.S. Mahmood, M.T. Chowdhury, M.A. Motalab, M.M. Sarker, M.J.H. Khan, N.H. Badrun and M. Rahman, "A Study on Geometry Model Approximation Effect of the Deterministic Method Compared to the Detailed Model of the MC simulation for LEU type fuel using SRAC and MVP", Internal Report, INST-118 /RPED-27, July 2009.
31. N. H. Badrun, M. T. Chowdhury, M. S. Mahmood, M. M. Sarker, M.J.H. Khan, M. A. Motalab and M. Rahman, "Application of Computer Code EUREKA-2/RR for Safety Analysis of 3 MW TRIGA MARK-II Research Reactor of BAEC: Part-I, Internal Report, INST-119/RPED-28, July 2009.
32. M.J.H. Khan, Mubarak.A. Khan, R.A. Khan, M.M. Sarker and M. Rahman, "A Computational Analysis on Attenuation Property of Fiber Reinforced Polymer Based Composites Using Monte Carlo Technique" Proceedings of the International Conference on Magnetism and Advanced Materials (ICMAM-2010), 03-07 March 2010, Dhaka, Bangladesh.
33. N.H. Badrun, M.T. Chowdhury, M.S. Mahmood, M.M. Sarker, M. J. H. Khan, M.A. Motalab and M. Rahman, "Application of Computer Code EUREKA-2/RR for Safety Analysis of 3 MW TRIGA MARK-II Research Reactor of BAEC: Part-II", Internal Report, INST-124/RPED-30, May, 2010.
34. N. H. Badrun, M. M. Sarker, M. J. H. Khan, M. S. Mahmood, M.T. Chowdhury, M. A. Motalab, and M. Rahman, "Heat Transfer Studies of the 3 MW TRIGA MARK-II Research Reactor of BAEC using the COOLOD-N2 Code", Internal Report, INST-126/RPED-32, June, 2010.
35. M. S. Mahmood, M. A. Motalab, M. Rahman M. M. Sarker, M. J. H. Khan, N. H. Badrun and M.T. Chowdhury, "A study on calculation models for burnup analysis of TRIGA Mark-II research reactor using the code MVP-BURN", Internal Report, INST-125/RPED-31, June, 2010.
36. M.S. Mahmud, M.T. Chowdhury, M.A. Motalab, M. Rahman, M.M.Sarker, M. J. H. Khan and N.H. Badrun, "Neutronic and Burnup Calculation of the TRIGA Mark-II Research Reactor using the SRAC Code System and the Monte Carlo Code MVP", AERE/TR-14, ISSN 2074-2371, June 2010.
37. N.H. Badrun, M.M.Sarker, M. J. H. Khan, M.S. Mahmud, M.T. Chowdhury, M.A. Motalab and M. Rahman, "Reactivity Initiated Transient Analyses using the Computer Code EUREKA-2/RR for 3 MW TRIGA Mark-II Research Reactor", AERE/TR-14, ISSN 2074-2371, June 2010.
38. N.H. Badrun, M.M.Sarker, M. J. H. Khan, M.S. Mahmud, M.T. Chowdhury, M.A. Motalab and M. Rahman, "ONBR and DNBR Studies of 3 MW Research Reactor of BAEC using the Computer Code COOLOD-N2", AERE/TR-14, ISSN 2074-2371, June 2010.