Institute of Nuclear Science and Technology

Reactor Physics and Engineering Division (RPED)

Phone: 880-2-7790683 Fax: 880-2-8130102,880-2-7789337

    Introduction:

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.



    Objectives:



   Research Activities:

The safe and efficient planning of nuclear reactor operation needs a wide spectrum of reactor engineering calculations. The activities of the division are conducted under the following research projects:

    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 gamma and neutron shielding respectively. The shield designs for the Brachytherapy Installation of Dhaka Medical College Hospital, Isotope Storage Pits of Industrial Radiotherapy, Decay Tank Room 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.
  39. N. H. Badrun, et. Al, “Four Stage Piecewise Continuous Stress-Strain Model for AISI-321 Grade Steel”, Proceeding on 3rd International Conference on SPPM2010, 24-26 February, 2011 BUET.
  40. M. S. Mahmood, et. al. “Neutron and Gamma Flux Calculation at the Radial Beam Port-I & II of the BAEC TRIGA Research Reactor”, Technical Report 2009-2010, AERE/TR-15&16, ISSN 2074-2371, June 2011
  41. N. H. Badrun, et. al. “Methods of Reliability Assessment in Probabilistic Safety Assessment” (PSA) Technical Report 2009-2010, AERE/TR-15&16, ISSN 2074-2371, June 2011.
  42. M. S. Mahmood, et. al “Calculation for Core Life Estimation and Extension of the TRIGA MARK-II Research Reactor of BAEC” Technical Report 2009-2010, AERE/TR-15&16, ISSN 2074-2371, June 2011,
  43. M. J. H. Khan, et. al. “Estimation of Shielding Thickness for TRIGA Spent Fuel Transport Cask using MicroShield Code”, Technical Report 2009-2010, AERE/TR-15-16, ISSN 2074-2371, June 2011.
  44. Sohel Rana, et. al “Vibration Analysis of Renovated Primary Cooling System of the 3MW TRIGA Mark-II Research Reactor”, Proceeding of the International Conferance on Mechanical Engineering 2011, ICME-11-AM- 047, 18-20 December, 2011, Dhaka
  45. M. S. Mahmood, et. al., “Neutronic Design Study of TRIGA Core Reconfiguration with Additional Irradiation Channels” INST Internal Report, INST-131/RPED-34, MAR, 2012.
  46. N. H. Badrun, et. al., Thermal Hydraulic Transient Study of 3MW TRIGA Mark-II Research Reactor of Bangladesh using the EUREKA-2/RR code, Annals of Nuclear Energy, Vol. 41 (40-47), March, 2012.
  47. Z. I. Lyric, et. al., “A study on TRIGA core reconfiguration with new irradiation channels”, Annals of Nuclear Energy, Vol. 43, p 183-186, May 2012.
  48. M. S. Mahmood, et. al., Operation History Effect on Burnup Calculation of BAEC TRIGA Research Reactor, Bangladesh Journal of Physics Vol. 11, P-103-113, ISSN 1816-1081, BPS, June, 2012.
  49. Sohel Rana et. al., “Analysis of Structural Intigrity on the Renovated Primary Cooling System of the 3MW TRIGA Mark-II Research Reactor”, Proceeding of the International Conferance on Mechanical Engineering & 14th Annual Paper Meet (6IMEC&14APM) 28-29 september, 2012, Dhaka.
  50. M. J. H. Khan et. al., “ A Computational Shield Design Analysis of the Disused Industrial Waste Co-60 Head at Mymensingh Medical College Hospital”, IWMPE 2012, Proceedings of the International Conference on Industrial Waste management and Process Efficiency, ISBN:978-984-33-5734-2,12-14 November, 2012, DUET, Gazipur, Bangladesh.


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