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jbd.mech@coep.ac.in

Faculty

Prof. Jagdeep Doshi
 

Designation: 

Professor Emeritus

Department: 

Mechanical

Email: 

jbd.mech@coep.ac.in

Phone Number: 

020-25507558

Website: 

www.coep.org.in

User ID: 

jbd.mech@coep.ac.in

Teaching Experience: 

25

Industry Experience: 

10

Research Experience: 

18

Qualifications: 

  B.Tech. Mechanical Engg., IIT Bombay August 1970;

M.S. Nuclear Engg., University of California, Berkeley, August 1971;

Ph.D. Nuclear Engg., University of California, Berkeley, June 1976

Teaching Responsibility: 

Mathematics for Engineers; Introduction to Nuclear Reactor Engineering (proposed) both courses for PG students

Additional Responsibility: 

Administrative Responsibilities :

Group Leader, Thermal and Fluids Engg. Group, Dept. of Mech. Engg., IIT, Bombay 1993-94; and 2003-2005;

Chairman, Library Committee IIT, Bombay, 1999-2002;

Chairman, Guest House Advisory Committee, IIT, Bombay, 2002-2007.

 

Publications: 

Sponsored Research Projects (Sponsor : Atomic Energy Regulatory Board)

1. Analysis of the Primary Containment of Liquid Metal-Cooled Fast Breeder Reactors
in a Core Disruptive Accident (1992-95).

2. Space-Time Kinetics Analysis of Large Pressurized Heavy Water Reactors (1995-97).

3. Coupled Neutronics and Thermal-Hydraulics Analysis of Large Pressurized Heavy
Water Reactors (1998-2003).

4. Development of a 3-D Space-Time Kinetics Model for the Analysis of Light
Water Reactors (2006-2009).

Books Published :

Analytical Methods in Engineering (Narosa; New Delhi, India, 1998).

Differential Equations for Scientists and Engineers (Narosa; New Delhi, India; 2010)

List of Publications -

1. "Role of Wall Heat Transfer and Other System Variables on Fuel Compaction and
Recriticality", Intl. Meet on Fast Reactor Safety and Related Physics, Chicago, USA,
October 1976.

2. "Space-Time Dynamics of Fast Breeder Reactors for Localized Disturbances",
Nuc.Sci.& Eng. 65, 1978.

3. "LMFBR Fuel Analysis", NUREG/CR-0011, February, 1978.

4. "Safety Characteristics of LMFBRs in Sodium Voiding Accident" Power Plant Safety
& Reliability Symposium, BARC, January, 1979.

5. "Optimal Solution of Problems with Boundary Conditions using Variational
Principles", Matscience Conf. on Mathematics in Economics Engineering and Life
Sciences, Mysore, March, 1980.

6. "Comparison of the Safety Aspects of Oxide and Carbide Fuelled LMFBRs", 75th
Meeting of DAESRC, Kalpakkam, July, 1981.

7. "Application of the Variational Method using Discontinuous Trial Functions for the
Two-Region Neutron Transport Problem", T.T.S.P., 12(1), pp. 1-33, June 1983.

8. "Solution of the Two Half-Space Milne Problem by the Variational Method" NSRP-5
Calcutta, November, 1983.

9. "Intercomparison of Various Trial Functions in the Application of the Variational
Method to the Neutron Transport Problem", Seminar on Transport Problems, Dept. of
Mathematics, North Bengal University, October, 1985.

10. "Solution of the Two Half-Space Problem with Linear Anisotropy using Variational
Method", NSRP-6, Kalpakkam, February, 1986.

11. "An Improved Model for the Molten Fuel-Coolant Interaction incorporating the
Particle Size Distribution, Fission Heating and the Heat Loss to Cold Structure", Conf. on Science & Technology of Fast Reactor Safety, Guernsey, Channel Islands (UK), May 1986. Fast Reactor Safety, vol.1, BNES, London, 1986.

12. "REZONE - Rezoning Programme in Two-Dimensions to Facilitate Coupling of the
Disassembly Code VENUS with the Containment Analysis Code REXCO-H",
IGC-Report, IGC-93, 1987.
13. "Application of Complementary Variational Principles to obtain Bounds for some
Integral Parameters", NSRP- 7, Mangalore University, November 1987.

14. "Molten Fuel-Coolant Interaction Behaviour of Various Fast Reactor Fuels", Ninth
National Heat & Mass Transfer Conf., I.I.Sc., Bangalore, December, 1987.

15. "Fast Reactor Fuel Aspects Related to MFCI and CDA", paper presented at the
Fourth meeting of the Committee for PFBR Fuel Development, IGCAR, Kalpakkam,
April 1988.

16. "Micro Gamma Scanning - An Algorithm for Unfolding Data Measured through
Rectangular Slit", Symposium on Radiochemistry and Radiation Chemistry, IGCAR,
Kalpakkam, January, 1989.

17. "Analysis of Space-Time Effects in a Transient Overpower Accident in the Prototype
Fast Breeder Reactor", NSRP-8, BARC, January, 1990.

18. "Variational Methods in Neutron Transport Theory", paper presented at the BARC-
IGCAR Discussion Meeting on Developments in Reactor Physics Calculational
Methods for Neutronic Design and Analysis, September 1990.

19. "Shock Loading of Reactor Vessel following Hypothetical Core Disruptive
Accident", presented at the 6th Miami International Symposium on Heat and Mass Transfer, December, 1990.

20. "Optimal Control of Xenon Spatial Oscillations", NSRP-9, Osmania University,
Hyderabad, November, 1991.

21. "Analysis of Dynamic Instability in Boiling Systems", ASME Winter Annual Meeting, Anaheim, Ca. USA, November, 1992.

22. "Hydrodynamic Analysis of Exploding Wire Phenomena", 19th National Conference
on Fluid Mechanics and Fluid Power, 3-5, December 1992, IIT Bombay.

23. "Analysis of Core Disruptive Accident in LMFBR using Near Characteristic Method
Journal of Nuclear Technology, 108, No.3, 1994, pp.338-349.

24. "Analysis of Core Disruptive Accidents in Liquid Metal cooled Fast Breeder
Reactors", 13th National Heat and Mass Transfer Conference, Surathkal, Karnataka, December 28-30, 1995, NHMT/ISHMT-ASME, pp.651-656.

25. "A Numerical Investigation of Nuclear Coupled Density Wave Oscillations",
Nuclear Engg. and Design, 154, 1995, pp.381-396.

26. “A Three Dimensional Space-Time Kinetics Analysis of LOCA in a PHWR”,
NSRP-12, Jodhpur, January, 1998.
27. “Transient Analysis of U-Tube Steam Generator using EICE Technique”, CHT’01,
Advances in Computational Heat Transfer-II, Queensland, Australia, May 2001.

28. “Analysis of Transients in Pressurised Heavy Water Reactors using Coupled
Neutronics-Thermal-Hydraulics Model”, Mathematics and Computation, Reactor
Physics and Nuclear and Biological Applications, (M & C 2005), Avignon, France,
Sept. 12-15, 2005.

29. “Control of Spatial Xenon Oscillations in large Power Reactors”, Advances in
Nuclear Analysis and Simulation, PHYSOR 2006, Vancouver, Canada, Sept. 10-14,
2006.

30. “Analysis of the Primary Containment of Liquid Metal Cooled Fast Breeder Reactor
in a Core Disruptive Accident”, 33rd National and 3rd International Conference on
Fluid Mechanics and Fluid Power, NCFMFP 2006, IIT, Bombay, Dec. 7-9, 2006.

31. “Non-Linear Analysis of Out-of-Phase Instabilities in Advanced Heavy Water
Reactor”, ASME International Mechanical Engineering Congress and Exposition,
IMECE, Seattle, Washington, USA, Nov. 11-15, 2007.

32. “Development of a Semi-Implicit Method for Transient Flow Boiling”, 19th National
& 8th ISHMT-ASME Heat and Mass Transfer Conference, JNTU, Hyderabad, India,
January 3-5, 2008.

33. “Non-Linear Analysis of Flow Boiling Instabilities in Water Cooled Nuclear
Reactors”, 19th National & 8th ISHMT-ASME Heat and Mass Transfer Conference,
JNTU, Hyderabad, India, January 3-5, 2008.

34. “Characteristics Based Implicit Finite Difference Scheme for the Analysis of
Instability in Water Cooled Reactors”, Nuclear Engineering and Technology, Korean Nuclear Society, vol. 40, October, 2008, pp. 477-488.

35. “Nonlinear analysis of nuclear coupled density wave instability in time domain for a
boiling reactor core undergoing core-wide and regional modes of oscillations” Progress in Nuclear Energy, vol. 51, issue 8, November 2009, pp. 769-787.

36. “Computational Modeling Procedures for Core Dynamics Analysis of large Nuclear
Reactors”, International Nuclear Conference 2009, INCO09, Malaysia, June 2009.

37. “Development of the Space-time Kinetics Model for VVER Reactors using Improved
Quasistatic Method”, NSRP-18, Udaipur, Nov. 19-21, 2009

38. “Development and Validation of Coupled Dynamics Code ‘TRIKIN’ for VVER
Reactors”, Nuclear Engineering and Technology, Korean Nuclear Society, vol. 42,
No.3, June 2010, pp. 259-270.

39. “Multiphysics Modeling in Nuclear Reactor Analysis”, Paper No. RS-05, Proceeding
of 2nd International Conference on ASIAN NUCLEAR PROSPECTS,
Mamallapuram, Chennai, India, 11-13 October 2010.

40. “Spatial Instability Analysis in Pressurized Water Reactors”, Annals of Nuclear
Energy, 38, Jan 2011, pp. 286-294.

41. “A Numerical Algorithm for the Solution of Simultaneous Nonlinear Equations to
Simulate Instability in Nuclear Reactor and its Analysis”, International Conference
on Computational Science and its Applications” ICCSA 2011, Santander, Spain
June 20-23, 2011.

42. “Investigations on the role of mixed convection and wall friction factor in single-
phase natural circulation loop dynamics”, Annals of Nuclear Energy, vol. 38(10), 2011, pp. 2247-2270.

43. “Formulation of Navier-Stokes equations by nodal integral method”, Proceedings of
the 13th Annual CFD Symposium, IISc, Bangalore, Aug. 11-12, 2011.

44. “Evaluation of decay heat removal capability of simulated advanced nuclear reactor
core configuration during an accident condition using thermal hydraulics code RELAP 5”, Proceedings of the 21st National and 10th ISHMT-ASME Heat and Mass Transfer Conference, Dec. 27-30, 2011, IIT, Madras, Tamil Nadu, India.

45. “Pressure correction based iterative scheme for Navier-Stokes equation using nodal
integral method”, Numerical Heat Transfer B, 62, 264-288, 2012.

46. “Solution of convection-diffusion equation in complex geometry by nodal integral
method”, Proceedings of the 14th Annual CFD Symposium, IISc, Bangalore,
Aug. 11-12, 2012.

47. “A novel Nodal Integral Method based solution for buoyancy driven flows,”
European Congress on Computational Methods in Applied Sciences and Engineering (ECCOMAS 2012), J. Eberhardsteiner et.al. (eds.), Vienna, Austria, September 10-14, 2012

48. “Formulation of Navier-Stokes equations by Nodal Integral Method using
quadrilateral elements” 39th National Conference on Fluid Mechanics and Fluid
Power, 13th-15th December 2012, SVNIT Surat.

49. “Nodal Integral Method using quadrilateral elements for transport equations:
Part 1-convection-diffusion equation”, Numerical Heat Transfer B, 64, July 2013,
pages 1-21

50. “Nodal Integral Method using quadrilateral elements for transport equations:
Part 2-Navier-Stokes equations”, Numerical Heat Transfer B, 64, July 2013, 22-47

 

Memberships and Affiliations: 

Life Member : Indian Nuclear Society; Life Member : Indian Society of Heat and Mass Transfer

Former Member of the Advisory Committee on Project Safety Review (ACPSR) for Pressurised Heavy Water Reactors and Prototype Fast Breeder Reactor 1995-2013

Member of the Advisory Committee on Nuclear Safety (ACNS) since 2007

Member of the Advisory Committee on Project Safety Review (ACPSR) for Pressurised Heavy Water Reactors and Prototype Fast Breeder Reactor from 1995 to 2013.

Member of the Advisory Committee on Nuclear Safety (ACNS) since 2007

Life Member : Indian Nuclear Society; Life Member : Indian Society of Heat and Mass Transfer

Former Member of the Editorial Board, Journal of Nuclear Engineering and Technology, Korean Nuclear Society.

 

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