NAME             : Avinash Jagannath Gaikwad

DATE OF BIRTH    : 1st July 1965

ADDRESS: Office: Room No. 421, Engineering Hall No. 7, Reactor Safety Division
(RSD), Bhabha Atomic Research Centre (BARC), Mumbai 400085.

Residence:	[1] 211 green hollow drive, iselin, New Jersey, USA 08830.
[2] 3 B, Kamet, Anushaktinagar, Mumbai 400094, India

Telephone: +91-22-25595184 (office),       +91-22-25571714 (Residence)

Email: [Send email using form at bottom], avinashg@barc.gov.in,
Gaikwad.avinash@gmail.com

EDUCATIONAL QUALIFICATIONS: 
B. E. Chemical Engineering (1987) PUNE University75% Stood first in the
Engineering College and first in PUNE University (Chemical Engineering Faculty)

EXPERIENCE:
I have been working on the development of process dynamics simulation computer
codes for Pressurised Heavy Water Reactor (PHWR / CANDU), Boiling Water Reactors
(BWR) and Pressurised Water Reactor (PWR) (based on mathematical models) and
using RELAP5/MOD3.2 code for nuclear power plant transient and safety analysis.
These codes are based on unsteady state mass, momentum and heat balance with heat
transfer packages. RELAP5/MOD3.2 simulation also includes neutronic inputs for
point kinetics reactor core dynamics. Model development, Refinery and a MEK
Dewaxing plant for operator-training simulators were also carried out. My work
also includes process optimization parametric studies, and the associated control
system models and Advanced process controller development.

PROJECTS/ TASKS /ASSIGNMENTS

540 MWe PHWR power plant operational transient analysis code Dyna540 development
used for surge line sizing, Selection of Steam Generator Pressure Control (SGPC)
program, Pressuriser level selection, IRVs design basis transient, Steam Bleed
Valve Stuck open malfunction, IRVs stuck open, one PCP trip, station blackout
etc.
750 MWe Advanced Heavy Water Boiling Water Reactor (AHWR) RELAP5/MOD3.2
simulation, steam drum model, drum pressure and level controller, turbine trip,
reactor trip, ICs cooling, etc.
700 MWe PHWR simulation model development using RELAP5 for PHT, Pressuriser, and
SGs.
700 MWe PHWR Passive Decay Heat Removal (PDHR) system simulation model for
design verification studies with boil off.
700 MWe PHWR Station blackout analysis with PDHR and steam line break analysis,
IRVs sizing design basis transient analysis.
920 MWe AHWR, RELAP5/MOD3.2 simulations, RRS model, feed water loss, power
maneuvering transients, turbine trip, cold condition loss of regulation accident
analysis (LORA).
Advanced Process Controller for 540 MWe PHWR linking PHT and the SG pressure
controllers, linking of SGPC with PHT PC and control logic modifications.
220 MWe PHWR power plant operator-training simulator, model for initial
warm/cool down of the steam generator, gives smooth performance from 0% FP to
100% FP, vice-versa and primary flow reversal.
220 MWe PHWR power plant abnormal incidence one primary circulating pump trip
analysis.
1000 MWe VVER Steam generator and Pressuriser RELAP5/MOD3.2 model and Primary
Circulating Pump seizure transient analysis.
920 MWe AHWR cold startup simulation, with/without startup-boiler from very low
power to 100% full power.
920 MWe AHWR small and large LOCA analysis with/without accumulators.
920 MWe PHWR drum level control program and level control philosophy.
Real time dynamic operator training simulator for a refinery mainly for
distillation column model.
MEK Dewaxing plant operator training simulator for distillation column, heat
exchangers, Filters, etc.
After successfully completing (secured second rank in the chemical Engineering
faculty of 32nd batch 1988-89) at the training at Bhabha Atomic Research Centre
(BARC) Mumbai, India, I joined the Power Plant Dynamics Section of Reactor Safety
Division  (Part of Reactor Design  & Development Group then now, it is a part of
Health Safety and Environment group), as a scientific officer (SO/C). Presently I
am working as scientific officer (SO/G), after obtaining four promotions, within
shortest possible period.

I have been working on the computer simulation code development for 540 MWe
Nuclear Power Plant Pressurised Heavy Water Reactor (PHWR), 220 MWe PHWR &
Advanced Heavy Water BWR involving the development of mathematical models of
process, equipment and the control systems, also using internationally
acclaimed/validated code RELAP5.

The task was carried out using a modular approach. For all the major components,
the process dynamics was simulated using the preliminary design data and steady
state operating conditions. These models were tested against available
plant/experimental data. Later on the control system models were integrated with
the process dynamics. Process and reactivity control system models were also
developed using RELAP5. 
 
The major sub-systems modeled include the Reactor heat transport system, the
Coolant circulating system, Pumps, Boilers, Condensers, Pressuriser and all the
associated control system. All the modules were then integrated together to form
a simulation program. This program is being used to simulate the anticipated
power plant operational transients, abnormal events, component failures/mal
functions, optimization of control systems, studies related to safety and to
establish better and new operating procedures.

I have also worked on real time dynamic operator training simulator for a
Refinery and MEK Dewaxing Plants. I was involved in commissioning and debugging
of the integrated code for simulation of the multi-component distillation
columns, heat exchangers, filters and other components. For the Refinery project
Atlantic Simulation Inc. (USA), distillation column software was used.

My job also involves delivering lectures on Reactor Engineering at BARC training
school for all Graduate Engineering Trainees.

Before joining BARC, I have worked for Citric India limited and Fibre Foam
Bombay Limited at Nasik, for about one year.

As a Trainee Engineer at Citric India Limited, Nasik (Sept 87 to Jan 88) in the
field of production during commissioning of Citric acid Fermentation unit my job
involved responsibilities of production and supervision. Production process
involved operations of dressing of raw material  (molasses), sterilization of the
feed by heating and cooling in plate type heat exchanger using high pressure
steam from boiler and cold water from cooling towers, Charging of the batch
reactor and to ensure the compressed air supply to aerobic fermentation process.

As an Engineer at Fibre Foam Private Limited, Sinar Nasik (Feb 88 to July 88) in
production and Quality Control during commissioning. My job involved the
responsibilities of transferring the technology of the production operation from
the consultant and to train the shift engineers in production and setting up of a
quality control laboratory.  Various operation processes involved mixing of
natural rubber with chemical charge from a ball mill, formation of Fibre sheet by
pneumatic conveying, hot pressing of Fibre sheet, Vulcanization of the product in
an autoclave.

COMPUTER FAMILIARITY:
Operating Systems		: UNIX, DOS, WINDOWS, and OS2
Programming Languages	: FORTRAN, C, Java, and SQL

AWARDS:
1) Padmashree Vithalrao Vekhe Patil Gold Medal for obtaining first position in
Engineering College (1987).
2) Bhide Prize for securing first position in Pune University Chemical
Engineering Faculty during Third and Final Year.

List of Publications for Shri A. J. Gaikwad:
3 Journals, 23 International & 32 National, Total: 58

International Journal Papers:
[1] A. J. Gaikwad, Rajesh Kumar, S. F. Vhora, G. Chakraborty and V. Venkat Raj,
“Transient analysis Following Tripping of a Primary Circulating Pump for 500 MWe
PHWR Power plant”, IEEE Trans. Nucl Sci., Vol. 50, Number 2, April 2003 (pp.
288-293).  [Journal-1]
[2] Rajesh Kumar, A. J. Gaikwad, S. F. Vhora, G. Chakraborty and V. Venkat Raj,
“Logic Modification to Avoid ECCS Lineup in the PHT System During Thermal
Shrinkage Transients of 220 MWe PHWR Nuclear Power Plant ”, IEEE Trans. Nucl
Sci., Vol. 50, Number 4, August 2003 (pp.1229-1237).  [Journal-2] 
[3]  A.J. Gaikwad, Rajesh Kumar, S. F. Vhora, G. Chakraborty and V. Venkat Raj,
“Selection of a Steam generator Pressure Control Program for a 500 MWe PHWR
Pressurized Heavy Water Reactor Power plant through Transient Analysis”, Proc.
Instn. Mech. Engrs. 2003 Vol 217 Part A No A6 ISSN 0957-6509: J. Power and
Energy.  [Journal-3]
International and National Conference Papers:
[4]. A. J. Gaikwad, A. K. Nayak, R. Kumar, A. Haridas, G. Chakraborty and V.
Venkat Raj, "Dynamic Modelling of Pressure Control System of a 500Mwe PHWR Power
Plant Thermal hydraulic Aspects", 11th National Heat and Mass Transfer
Conference, Dec 21-23, 1991, IIT Madras.
[5] A. K.  Nayak, A.J. Gaikwad, P.K. Vijayan and V. Venkat Raj, "Performance
Analysis Of Bleed Condensers Used In Indian PHWRs", 11th National Heat and Mass
Transfer Conference, Dec 21-23, 1991, IIT Madras.
[6] S.G. Markandeya, A. J. Gaikwad, S. K. Chaki, R.L. Sehgal and V. Venkat Raj,
"An Assessment of Relative Merits of Thermodynamic Conditions on the Prediction
of Transient Behavior of the 500 MWe PHWR Pressuriser", National Symposium on
Safety of Nuclear Power Plants and Other Facilities, BARC, Bombay, March 11-13
1992.
[7] A. J. Gaikwad, G. Chakraborty and V. Venkat Raj, "Parametric Study Of
Behavior Of Pressure Control System Of A 500MWe PHWR Power plant", National
Symposium on Safety of Nuclear Power Plants and Other Facilities, BARC, Bombay,
March 11-13 1992.
[8] A.J. Gaikwad, S.G. Markandeya, S. K. Chaki, R.L. Sehgal and V.  Venkat Raj, 
"Mathematical Modeling of Pressuriser Dynamic Code and Development of Computer
Code "PRESS" as a Part of Power Plant Dynamic Analysis Code", IMACS International
Symposium On Mathematical Modeling and Scientific Computing December 7-11 1992,
Bangalore.
[9] G. Chakraborty, A. J. Gaikwad, and V. Venkat Raj, "Nuclear Power Plant
Dynamics Computer Aided Modeling and Analysis", National Symposium on Computer
Application in Power Plants, B.A.R.C, DAE, Bombay, December 8-10, 1992.
[10] A. J. Gaikwad, Rajesh Kumar, Anu Bhadra, G. Chakraborty, and V. Venkat 
Raj,  "Transient Analysis of a U-tube natural circulation steam generator,"  
Advances   in   chemical engineering in nuclear and process industries, June
9-11, 1994, BARC, Bombay.
[11] A. J. Gaikwad, S. K. Chaki, R. L. Sehgal and V. Venkat Raj, "Flow and
Pressure profile for the primary heat transport system of Rajasthan Atomic Power
Station for the operation with few isolated reactor channels near the end shield
cracks", Advances in chemical engineering in nuclear and process industries, June
9-11, 1994, BARC, Bombay.
[12] A. J. Gaikwad, Anu Bhadra, S. K. Chaki, G. Chakraborty and V. Venkat Raj, "
Modeling and analysis of the Transient response of the Steam Generator of a 500
MWe PHWR power plant", Second ASME  Thirteenth  National  Heat  and Mass Transfer
 Conference,  December 28-30, 1995, KREC Surathkal, Karnataka. 
[13] I. A.  Patwekar, A.J. Gaikwad, S.G. Markandeya, S. K. Chaki, R.L. Sehgal
and V. Venkat Raj, "Condensation Heat Transfer in Presence of non-condensable
gases a case study", Indian Chemical Engineering Congress 1995, 48th Annual 
Session  of Indian Institute of Chemical Engineers, December 27-30,1995, Indira
Gandhi Centre for Atomic Research, Kalpakkam 603 102.
[14] A.  J.  Gaikwad, Rajesh Kumar, G. Chakraborty and V. Venkat Raj,
“Optimization of the 500 MWe PHWR power plant pressure control system" Indian
Chemical Engineering Congress 1996, CHEMCON-96, 49th Annual Session of Indian
Institute of Chemical Engineers, December 18-21, 1996, Ankleshwar 393 002.
[15] Rajesh Kumar, A. J. Gaikwad, G. Chakraborty and V. Venkat Raj "Transient
Analysis of an Indian 220MWe PHWR Power Plant Following Tripping of One Primary
Circulating Pump", Third ASME Fourteenth National Heat and Mass Transfer
Conference, December, 1997, to be held at IIT Kanpur.
[16] Rajesh Kumar, Avinash J. Gaikwad and G. Chakraborty, “Design Basis
Transient Analysis of Primary Relief System of Indian 220 MWe PHWR Power Plants”,
Fourth ISHMT/ASME - Fifteenth National Heat and Mass Transfer Conference,
January12-15, 2000, IAT, Pune.
[17] Avinash J Gaikwad, Rajesh Kumar and G. Chakraborty, “Mathematical Modelling
of Boiler Process Dynamics for use in Operator Training Simulator of a Nuclear
Power Plant”, Fourth ISHMT/ASME - Fifteenth National Heat and Mass Transfer
Conference, January12-15, 2000, IAT, Pune.
[18] Avinash J. Gaikwad, Rajesh Kumar, G. Chakraborty, H. S. Kushwaha, V. Venkat
Raj, “Mathematical Modelling of a 500 MWe Indian PHWR Power Plant for Operational
Transient Analysis”, International Conference on Mathematical Modelling, January
29-31, 2001, University of Roorkee, Roorkee, India. 
[19] Rajesh Kumar, Avinash J Gaikwad, G. Chakraborty, H. S. Kushwaha,
“Mitigation Schemes for Avoiding very low Pressure Condition in the Primary Heat
Transport System during Thermal Shrinkage Transients of 220 MWe PHWR Nuclear
Power Plants”, Third National Conference on Thermal Systems, February 17-18,
2001, Institute of Technology, BHU, Varanasi, India
[20] A. J. Gaikwad, Rajesh Kumar, A. Srivastava, G. Chakraborty, S. K. Gupta and
V. Venkat Raj, “Thermal - Hydraulic Studies Following Turbine Trip Transient for
Advanced Reactor Power Plant”, 28th National Conference on Fluid Mechanics and
Fluid Power 2001, Chandigarh
[21] A. J. Gaikwad, Rajesh Kumar, A. Srivastava, G. Chakraborty, S. K. Gupta and
V. Venkat Raj,” Steam Drum Pressure Controller response for AHWR turbine trip
operational transient”, Nuclear technologies challenges in 21st century, October
10-12, 2001, Centre for Advanced Technology, Indore.
[22] Rajesh Kumar, A. J. Gaikwad, H. G. Lele, B. Chatterjee, G. Chakraborty, S.
K. Gupta and H. S. Kushwaha, “Advanced Heavy Water Reactor (AHWR) LOCA Analysis
with Loss of Emergency Core Cooling System (ECCS) for 200% Inlet Header Break”,
16th National Heat and Mass Transfer Conference and 5th ISHMT/ASME Heat and Mass
Transfer Conference January 3-5, 2002, Kolkata. 
[23] A. J. Gaikwad, Rajesh Kumar, G. Chakraborty, and H. S. Kushwaha, “Transient
Analysis for Selection of SG Pressure Control Program for a 500 MWe PHWR Power
Plant”, 16th National Heat and Mass Transfer Conference and 5th ISHMT/ASME Heat
and Mass Transfer Conference January 3-5, 2002, Kolkata. 
[24] A. J Gaikwad, Rajesh Kumar, A. Srivastava, H. G. Lele, G. Chakraborty, S.
K. Gupta and V. Venkat Raj, “Thermal-hydraullic transient studies for AHWR power
plant drum level control program selection”, International Symposium on Recent
Trends in Heat and Mass Transfer, January 6-8, 2002, Indian Institute of
Technology, Guwahati.
[25] Rajesh Kumar, A.J. Gaikwad, A. Srivastava, P. Majumdar, H.G. Lele, G.
Chakraborty, S. K. Gupta and V. Venkat Raj, “Transient Behavior Of Advanced Heavy
Water Reactor Under Different Operating Conditions”, 1st National Conference on
Nuclear Reactor Safety, BARC, Mumbai, November 25-27, 2002.
[26] Rajesh Kumar, A. J. Gaikwad, G. Chakraborty, S. K. Gupta and V. Venkat Raj,
“Effect of Grid frequency -A Transient Study for Indian PHWRs”, 1st National
Conference on Nuclear Reactor Safety, BARC, Mumbai, November 25-27, 2002.
[27] Rajesh Kumar, A.J. Gaikwad, S.F. Vhora and G. Chakraborty, “Transient
analysis of 220 MWe Indian PHWRs to prevent ECCS Line up following Reactor Trip
with several measures Including incorporation of a small size Pressuriser”, 1st
National Conference on Nuclear Reactor Safety, BARC, Mumbai, November 25-27,
2002.
[28] Rajesh Kumar, A.J. Gaikwad, S.F. Vhora and G. Chakraborty, “Avoidance of
Reactor Trip on High PHT System Pressure for 220 MWe Indian PHWRs With addition
of Pressuriser”, 1st National Conference on Nuclear Reactor Safety, BARC, Mumbai,
November 25-27, 2002.
[29] A.J. Gaikwad, Rajesh Kumar, S.F. Vhora and G. Chakraborty, “Turbine Trip
With Step/Set Back Operational Transient Analysis For 500 MWe PHWR”, 1st National
Conference on Nuclear Reactor Safety, BARC, Mumbai, November 25-27, 2002.
[30] A.J. Gaikwad, Rajesh Kumar, S.F. Vhora and G. Chakraborty, “Primary
Circulating Pump Trip Transient Analysis For 500 MWe PHWR”, 1st National
Conference on Nuclear Reactor Safety, BARC, Mumbai, November 25-27, 2002.