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Technical aspects of improving

      acceptance of nuclear power

       : dealing with catastrophe syndrome


               Anil Kakodkar*
                      INSAC 2012
                   November 7,2012
*With inputs from Shri H. S. Kushwaha & Dr. R. K. Singh
Key issues in public acceptance
• Dealing with mind sets
 Small is beautiful
 Nuclear is evil
 Perceived external influence
 Trust deficit , NIMBY………
• Catastrophe syndrome
 Consequences (real or perceived)
 larger than a threshold are
 unacceptable regardless of low
 probability
 TMI, Chernobyl and now Fukushima
 have created adverse impact on public
mind
 That Fukushima was caused by nature’s
fury is an added factor
NEVER AGAIN
•   Both TMI & Chernobyl were triggered by internally
    initiated events

•   Several lessons learnt, improvements implemented
    and confidence restored

•   Signs of nuclear renaissance were visible

•   Chernobyl also led to valuable insights into
    consequences in public domain

•   Fukushima was triggered by an extreme external
    natural event

•   We must now ensure that an essential goal for nuclear
    safety is “NEVER AGAIN” should there be any
    significant off site emergency
Comprehensive approach to safety
1. Reassess the design basis assumptions for both new and existing
   plants at two levels
•  plant shall be able to cope without significant radioactive releases and without
  irreparable damage
•      plant should be able to cope without requiring significant off-site emergency response


2. Reassess plant response to severe accidents that cause extensive
   reactor damage
3. Develop and implement effective on-site accident management
   strategies
4. Reassess capabilities for off-site emergency management
5. Approach to old and new nuclear power plants
6. Reassess safety culture and quality of safety management
7. Ways to strengthen the international safety regime
8. Better ways to inform the media and the public on the severity of
Dual level design basis
• Design basis                                        No impact in
    (risk lowered to an                               public domain or
     acceptable level)                                irreparable damage
                                                      to plant


• Extreme event*                                     No significant off-site
    (maximum potential)                                emergency

    *Extra margin between design and ultimate load capacity
     should be sufficient to cope with this
•   Note: Nuclear Power Plants are Designed to withstand the loading due to
    Natural and Man-induced external Events with low enough probability of
    occurrence. Some of the man induced hazard are ruled out using SDV
    Criteria.
•   On a similar logic one could identify maximum potential loading for specific
    engineered safety features / events at a site* and demonstrate them to be
    within the margin beyond design basis capacity.
•   *Core cooling capability, hydrogen mitigation, containment isolation,
    earthquakes, tsunami, etc.etc.
Potential Natural and Man-Induced
            Hazard Phenomena
 

      • ATOMOSPHERIC               Cyclones
                                   Tornado
                                   Tropical Storm
                                   Lightening

      • SEISMIC                    Ground Shaking / Fault Rupture
                                   Liquefaction
                                   Tsunami

•   GEOLOGICAL               Rock Fall
                                    Land Slide
                                    Debris Avalanches

      • HYDROLOGICAL               Flooding

                                   Strom Surge
                                   Erosion and Sedimentation

      • Man-Induced Events         Oil Storage & Refineries
                                   Explosion
                                   Missiles
                                   Air Craft Crash
                                   Terrorist Attack
BARC Containment (BARCOM) Test-Model (Design Pressure Pd 0.1413 MPa)
 at BARC-Tarapur Test Facility with details of Embedded Sensors and Cable Panels
    An overview of Sensors & Instrumentation Cable for concrete, rebar and tendons




Phase-II Test- Typical Response        Pre-Test Predictions by Round Robin Participants
     Jason-1 track 109 satellite (altitude 1300km) record
                           and
                      TSUSOL Predictions
7
                                                                                               5.72                         5.74
                                                                            6         5.15
                                                                            5   4.5
                                                                                                        3.88      4.00
                                                                            4
                                                                            3
                                                                            2                    1.22                         1.24
                                                                                        0.65
                                                                            1
                                                                            0
                                                                           -1                             -0.62     -0.50
                                                                                SRI IGCAR IIT-M ICMAM NGRI ACRi
                                                                    Prediction 4.5     5.15     5.72     3.88      4.00      5.74
                                                                    Deviation          0.65     1.22    -0.62     -0.50      1.24

        7                     6.00
        6
             4.6
        5           3.99                         3.46      3.5
        4                              2.83
        3
        2                       1.40
        1
        0
       -1
                      -0.61
       -2                                          -1.14     -1.1
       -3
                                         -1.77
             SRI    IGCAR IIT-M ICMAM NGRI                 ACRi
Prediction    4.6    3.99      6.00     2.83      3.46      3.5
Deviation           -0.61      1.40    -1.77     -1.14     -1.1
Long term nuclear power development
            - The challenge of the numbers.
•   A per  capita  electricity  use  of  about 5000  kWh/year appears to be needed  for  
    reaching  a  state  of reasonably high    human    development. Considering  the  
    progressive  depletion  of  fossil  fuel reserves,  and  the  urgent  need  for  
    addressing  the  global warming related concerns, nuclear energy is expected to 
    substantially  contribute  to meeting the future global energy requirements.

•   Assuming that  at least half of  the  total  energy  demand  may  need  to  be  met  
    with nuclear,  the  world  will need  between  3000  to  4000  nuclear  power 
    reactors of different capacities for electricity generation. The number may at least 
    double with the use of nuclear energy  to  provide  an  alternative  to  fluid  fossil  
    fuels.

•   A large number of these reactors may need to be located in regions with high 
    population densities and modest technological infrastructure with their sizes 
    consistent with local needs. 


                                                                                           10

AHWR is a 300 MWe vertical pressure tube type, boiling light water cooled and
heavy water moderated reactor (An innovative configuration that can provide
           low risk nuclear energy using available technologies)

AHWR 300-LEU would enable realisation of these advantages with competitive Uranium
  use & without the need for concurrent recycle. This may be a necessity in many
                                    countries.

                            Major objectives
                              Significant fraction of energy
                               from Thorium
                                                                    Top Tie Plate
                              Several passive features                 Displacer 
                                 3 days operator grace          Water  Rod
                                                                 Tube
                                  period                          Fuel 
                                 No radiological impact in       Pin

                                  public domain
  AHWR can be                    Can address insider threat
  configured to accept a          scenarios
  range of fuel types            Lower proliferation
  including LEU, U-               concerns
  Pu , Th-Pu , LEU-Th
  and 233U-Th in full         Design life of 100 years.          Bottom Tie Plate
  core                        Easily replaceable coolant          AHWR Fuel assembly
Peak clad temperature hardly rises
 even with the extreme postulate of
   complete station blackout and
simulteneous failure of both primary
 and secondary shut down systems.
PSA calculations for AHWR indicate practically zero
    probability of a serious impact in public domain
   Plant familiarization &                                     Level-3 : Atmospheric Dispersion With                                             SWS: Service
   identification of design                                           Consequence Analysis                                                       Water System

   aspects important to                                                                                                                          APWS: Active
                                                                                                                                                 Process Water
   severe accident                                                                                                                               System

                                                                       Release from Containment                                                  ECCS
                                                                                                                                                 HDRBRK:
                                                                                                                                                 ECCS Header
   PSA level-1 : Identification                                                                                                                  Break

   of significant events with                                                                                                                    LLOCA: Large
                                                                                                                                                 Break LOCA
   large contribution to CDF                                   Level-2 : Source Term (within                                             SLOC    MSLBOB: Main
                                                               Containment) Evaluation through              SWS                          A       Steam Line
                                                                                                            63%                          15%
                                                               Analysis                                                                          Break Outside
                                                                                                                        Contribution to CDF      Containment

                                              Level-1, 2 & 3 PSA activity block diagram



                                10-10
                                 10
                                   -10
      Frequency of Exceedence




                                10-11
                                 10
                                   -11




                                   -12
                                10-12
                                 10


                                10-13
                                 10
                                   -13




                                10-14
                                 10
                                   -14




                                     1 10
                                        mSv       0.1 Sv       1.0 Sv        10 Sv
                                         -3           -2          -1           0
                                                     10         10            10
                                              Thyroid Dose (Sv) at 0.5 Km                         Iso-Dose for thyroid -200% RIH + wired shutdown system
     Variation of dose with frequency exceedence                                                  unavailable (Wind condition in January on western Indian
                                                                                                                                                           13
(Acceptable thyroid dose for a child is 500 mSv)                                                                            side)
    Generic Assessment Procedure for Determining
  Protective Actions during a Reactor Accident
 
• Accident Assessment
 
• Emergency Classification
 
• Protective Action Decision Making

• Assessment of Environment Data
 
• Monitoring
 
• Operational Intervention Levels (OILs)
LNT Model is Inaccurate
  The major cause of worry is the general public perceiving that
    radiation is harmful no matter how low the dose.

 Reality                                             Real radiation danger levels
                                          Crosses show the mortality of Chernobyl firefighters
                                                 (numbers died/total in each dose range ) 
.Colorado ,USA has a population over                         ( curve is for rats)
5 millions residents. According to
LNT model Colorado should have an
excess of 200 cancer deaths per year
but has a rate less than the national
average.
 
. Ramasar ,Iran, residents receive a
  yearly dose of between 100-260 mSv.
  This is several time higher than
  radiation level at Chernobyl and
  Fukushima exclusion zone. People
  living in Ramsar have no adverse
  health effect , but live longer and
  healthier lives.
 
. We also know that China , Norway,
  Sweden, Brazil and India have similar    Above 4,000 mSv 27/42 died from Acute
  areas where radiation level is many           Radiation Syndrome (ARS),
  times higher than 2.4 mSv/yr world                    not cancer.
  average.                                     Below 4,000 mSv 1/195 died.
 
    
Projected health consequences from low
   doses to large sections of population are
                 questionable

IN CASE OF CHERNOBYL

SOME ESTIMATED CONSEQUENCES                 Driven by over
AN ESTIMATE IN 2006—93,000 WILL DIE DUE      conservative
TO CANCER UP TO THE YEAR2056 ANOTHER
                                               linear no
ESTIMATE IN 2009---985,000 DIED TILL 2004
                                               threshold
                                           principle (which
ACTUAL CONSEQUENCE                               is not
TOTAL DEATHS;
62 (47 PLANT, 15 DUE TO THYROID CANCER )  substantiated by
ACUTE RADIATION SYNDROME;                   surveys in high
134 (OUT OF WHICH 28 HAVE DIED)           natural radiation
INCREASED CANCER INCIDENCE;                   background
 AMONG RECOVERY WORKERS
THYROID CANCER; (CURABLE, WAS AVOIDABLE)  areas) we tend to
 6000 ( 15 HAVE DIED)                     create avoidable
                                           trauma in public
Looking back at Fukushima
. It has become apparent at Fukushima that the
evacuation from the “exclusion Zone” has been
excessive. Some of the areas that have been
evacuated probably suffered so little contamination
that they could be reoccupied.
 
. As per WHO report most of the people in Fukushima
prefecture would have received a radiation dose of
between 1-10 mSv during first year. Two places the
dose were between 10- 50 mSv still below harmful
level. Almost all other places were below the
internationally agreed reference level for the public
exposure due to radon in dwelling (about 10 mSv).
Chernobyl Psychosomatic effects
‘Besides the 28 fatalities among rescue workers and employees of the power station due to
   very high doses of radiation (2.9 - 16 Gy), and three deaths due to other reasons
   (UNSCEAR 2000b), the only real adverse health consequences of the Chernobyl
   catastrophe among approximately five million people living in the contaminated regions
   were the epidemics of psychosomatic afflictions. These appear as diseases of the
   digestive and circulatory systems and other post-traumatic stress disorders such as
   sleep disturbance, headache, depression, anxiety, escapism, “learned helplessness”,
   unwillingness to cooperate, overdependence, alcohol and drug abuse and suicides
   (Forum 2005). These diseases and disturbances could not have been due to the minute
   irradiation doses from the Chernobyl fallout (average dose rate of about 1 - 2 mSv/year),
   but they were caused by radiophobia (a deliberately induced fear of radiation)
   aggravated by wrongheaded administrative decisions and even, paradoxically, by
   increased medical attention which leads to diagnosis of subclinical changes that
   persistently hold the attention of the patient.

Bad administrative decisions made several million people believe that they were “victims
   of Chernobyl” although the average annual dose they received from “Chernobyl”
   radiation was only about one third of the average natural dose. This was the main
   factor responsible for the economic losses caused by the Chernobyl catastrophe,
   estimated to have reached $148 billion by 2000 for the Ukraine, and to reach $235
. The Health Physics Society's position Statement
 first adopted in Jan. 1996, as revised in July 2010,
 states: In accordance with current knowledge of
 radiation risks, the Health Physics Society
 recommend against quantitative estimation of
 health risks below an individual dose of 5 rem(50
 mSv) in one year or a lifetime dose of 10 rem (100
 mSv) above that received from natural sources.

. French Academy of Sciences and the National
 Academy of Medicine published a report in 2005
 that rejected the LNT model in favour of a
 threshold dose response and a significantly
 reduced risk at low radiation exposures.
What do we need to do?
• Realistic worst case assessment in public
  domain at each site taking margins beyond
  design basis into account
• Pragmatic evidence based intervention
  levels ( not biased by LNT) to be articulated
  in advance
• Credibly demonstrate best estimate impact
  in public domain (expected to be much
  lower)
• Develop and deploy systems that do not
  cause any adverse impact in public domain
Thank you
 Visit www.anilkakodkar.in

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Technical aspects of improving acceptance of nuclear power insac 2012

  • 1. Technical aspects of improving acceptance of nuclear power : dealing with catastrophe syndrome Anil Kakodkar* INSAC 2012 November 7,2012 *With inputs from Shri H. S. Kushwaha & Dr. R. K. Singh
  • 2. Key issues in public acceptance • Dealing with mind sets  Small is beautiful  Nuclear is evil  Perceived external influence  Trust deficit , NIMBY……… • Catastrophe syndrome  Consequences (real or perceived) larger than a threshold are unacceptable regardless of low probability  TMI, Chernobyl and now Fukushima have created adverse impact on public mind  That Fukushima was caused by nature’s fury is an added factor
  • 3. NEVER AGAIN • Both TMI & Chernobyl were triggered by internally initiated events • Several lessons learnt, improvements implemented and confidence restored • Signs of nuclear renaissance were visible • Chernobyl also led to valuable insights into consequences in public domain • Fukushima was triggered by an extreme external natural event • We must now ensure that an essential goal for nuclear safety is “NEVER AGAIN” should there be any significant off site emergency
  • 4. Comprehensive approach to safety 1. Reassess the design basis assumptions for both new and existing plants at two levels • plant shall be able to cope without significant radioactive releases and without irreparable damage • plant should be able to cope without requiring significant off-site emergency response 2. Reassess plant response to severe accidents that cause extensive reactor damage 3. Develop and implement effective on-site accident management strategies 4. Reassess capabilities for off-site emergency management 5. Approach to old and new nuclear power plants 6. Reassess safety culture and quality of safety management 7. Ways to strengthen the international safety regime 8. Better ways to inform the media and the public on the severity of
  • 5. Dual level design basis • Design basis No impact in (risk lowered to an public domain or acceptable level) irreparable damage to plant • Extreme event* No significant off-site (maximum potential) emergency *Extra margin between design and ultimate load capacity should be sufficient to cope with this • Note: Nuclear Power Plants are Designed to withstand the loading due to Natural and Man-induced external Events with low enough probability of occurrence. Some of the man induced hazard are ruled out using SDV Criteria. • On a similar logic one could identify maximum potential loading for specific engineered safety features / events at a site* and demonstrate them to be within the margin beyond design basis capacity. • *Core cooling capability, hydrogen mitigation, containment isolation, earthquakes, tsunami, etc.etc.
  • 6. Potential Natural and Man-Induced Hazard Phenomena   • ATOMOSPHERIC Cyclones Tornado Tropical Storm Lightening • SEISMIC Ground Shaking / Fault Rupture Liquefaction Tsunami • GEOLOGICAL Rock Fall Land Slide Debris Avalanches • HYDROLOGICAL Flooding Strom Surge Erosion and Sedimentation • Man-Induced Events Oil Storage & Refineries Explosion Missiles Air Craft Crash Terrorist Attack
  • 7. BARC Containment (BARCOM) Test-Model (Design Pressure Pd 0.1413 MPa) at BARC-Tarapur Test Facility with details of Embedded Sensors and Cable Panels An overview of Sensors & Instrumentation Cable for concrete, rebar and tendons Phase-II Test- Typical Response Pre-Test Predictions by Round Robin Participants
  • 8.      Jason-1 track 109 satellite (altitude 1300km) record and TSUSOL Predictions
  • 9. 7 5.72 5.74 6 5.15 5 4.5 3.88 4.00 4 3 2 1.22 1.24 0.65 1 0 -1 -0.62 -0.50 SRI IGCAR IIT-M ICMAM NGRI ACRi Prediction 4.5 5.15 5.72 3.88 4.00 5.74 Deviation 0.65 1.22 -0.62 -0.50 1.24 7 6.00 6 4.6 5 3.99 3.46 3.5 4 2.83 3 2 1.40 1 0 -1 -0.61 -2 -1.14 -1.1 -3 -1.77 SRI IGCAR IIT-M ICMAM NGRI ACRi Prediction 4.6 3.99 6.00 2.83 3.46 3.5 Deviation -0.61 1.40 -1.77 -1.14 -1.1
  • 10. Long term nuclear power development - The challenge of the numbers. • A per  capita  electricity  use  of  about 5000  kWh/year appears to be needed  for   reaching  a  state  of reasonably high    human    development. Considering  the   progressive  depletion  of  fossil  fuel reserves,  and  the  urgent  need  for   addressing  the  global warming related concerns, nuclear energy is expected to  substantially  contribute  to meeting the future global energy requirements. • Assuming that  at least half of  the  total  energy  demand  may  need  to  be  met   with nuclear,  the  world  will need  between  3000  to  4000  nuclear  power  reactors of different capacities for electricity generation. The number may at least  double with the use of nuclear energy  to  provide  an  alternative  to  fluid  fossil   fuels. • A large number of these reactors may need to be located in regions with high  population densities and modest technological infrastructure with their sizes  consistent with local needs.  10
  • 11.  AHWR is a 300 MWe vertical pressure tube type, boiling light water cooled and heavy water moderated reactor (An innovative configuration that can provide low risk nuclear energy using available technologies) AHWR 300-LEU would enable realisation of these advantages with competitive Uranium use & without the need for concurrent recycle. This may be a necessity in many countries.  Major objectives  Significant fraction of energy from Thorium Top Tie Plate  Several passive features Displacer   3 days operator grace Water  Rod Tube period Fuel   No radiological impact in Pin public domain AHWR can be  Can address insider threat configured to accept a scenarios range of fuel types  Lower proliferation including LEU, U- concerns Pu , Th-Pu , LEU-Th and 233U-Th in full  Design life of 100 years. Bottom Tie Plate core  Easily replaceable coolant AHWR Fuel assembly
  • 12. Peak clad temperature hardly rises even with the extreme postulate of complete station blackout and simulteneous failure of both primary and secondary shut down systems.
  • 13. PSA calculations for AHWR indicate practically zero probability of a serious impact in public domain Plant familiarization & Level-3 : Atmospheric Dispersion With SWS: Service identification of design Consequence Analysis Water System aspects important to APWS: Active Process Water severe accident System Release from Containment ECCS HDRBRK: ECCS Header PSA level-1 : Identification Break of significant events with LLOCA: Large Break LOCA large contribution to CDF Level-2 : Source Term (within SLOC MSLBOB: Main Containment) Evaluation through SWS A Steam Line 63% 15% Analysis Break Outside Contribution to CDF Containment Level-1, 2 & 3 PSA activity block diagram 10-10 10 -10 Frequency of Exceedence 10-11 10 -11 -12 10-12 10 10-13 10 -13 10-14 10 -14 1 10 mSv 0.1 Sv 1.0 Sv 10 Sv -3 -2 -1 0 10 10 10 Thyroid Dose (Sv) at 0.5 Km Iso-Dose for thyroid -200% RIH + wired shutdown system Variation of dose with frequency exceedence unavailable (Wind condition in January on western Indian 13 (Acceptable thyroid dose for a child is 500 mSv) side)
  • 14.     Generic Assessment Procedure for Determining Protective Actions during a Reactor Accident   • Accident Assessment   • Emergency Classification   • Protective Action Decision Making • Assessment of Environment Data   • Monitoring   • Operational Intervention Levels (OILs)
  • 15. LNT Model is Inaccurate The major cause of worry is the general public perceiving that radiation is harmful no matter how low the dose. Reality Real radiation danger levels Crosses show the mortality of Chernobyl firefighters (numbers died/total in each dose range )  .Colorado ,USA has a population over ( curve is for rats) 5 millions residents. According to LNT model Colorado should have an excess of 200 cancer deaths per year but has a rate less than the national average.   . Ramasar ,Iran, residents receive a yearly dose of between 100-260 mSv. This is several time higher than radiation level at Chernobyl and Fukushima exclusion zone. People living in Ramsar have no adverse health effect , but live longer and healthier lives.   . We also know that China , Norway, Sweden, Brazil and India have similar Above 4,000 mSv 27/42 died from Acute areas where radiation level is many Radiation Syndrome (ARS), times higher than 2.4 mSv/yr world not cancer. average. Below 4,000 mSv 1/195 died.       
  • 16. Projected health consequences from low doses to large sections of population are questionable IN CASE OF CHERNOBYL SOME ESTIMATED CONSEQUENCES Driven by over AN ESTIMATE IN 2006—93,000 WILL DIE DUE conservative TO CANCER UP TO THE YEAR2056 ANOTHER linear no ESTIMATE IN 2009---985,000 DIED TILL 2004 threshold principle (which ACTUAL CONSEQUENCE is not TOTAL DEATHS; 62 (47 PLANT, 15 DUE TO THYROID CANCER ) substantiated by ACUTE RADIATION SYNDROME; surveys in high 134 (OUT OF WHICH 28 HAVE DIED) natural radiation INCREASED CANCER INCIDENCE; background AMONG RECOVERY WORKERS THYROID CANCER; (CURABLE, WAS AVOIDABLE) areas) we tend to 6000 ( 15 HAVE DIED) create avoidable trauma in public
  • 17. Looking back at Fukushima . It has become apparent at Fukushima that the evacuation from the “exclusion Zone” has been excessive. Some of the areas that have been evacuated probably suffered so little contamination that they could be reoccupied.   . As per WHO report most of the people in Fukushima prefecture would have received a radiation dose of between 1-10 mSv during first year. Two places the dose were between 10- 50 mSv still below harmful level. Almost all other places were below the internationally agreed reference level for the public exposure due to radon in dwelling (about 10 mSv).
  • 18. Chernobyl Psychosomatic effects ‘Besides the 28 fatalities among rescue workers and employees of the power station due to very high doses of radiation (2.9 - 16 Gy), and three deaths due to other reasons (UNSCEAR 2000b), the only real adverse health consequences of the Chernobyl catastrophe among approximately five million people living in the contaminated regions were the epidemics of psychosomatic afflictions. These appear as diseases of the digestive and circulatory systems and other post-traumatic stress disorders such as sleep disturbance, headache, depression, anxiety, escapism, “learned helplessness”, unwillingness to cooperate, overdependence, alcohol and drug abuse and suicides (Forum 2005). These diseases and disturbances could not have been due to the minute irradiation doses from the Chernobyl fallout (average dose rate of about 1 - 2 mSv/year), but they were caused by radiophobia (a deliberately induced fear of radiation) aggravated by wrongheaded administrative decisions and even, paradoxically, by increased medical attention which leads to diagnosis of subclinical changes that persistently hold the attention of the patient. Bad administrative decisions made several million people believe that they were “victims of Chernobyl” although the average annual dose they received from “Chernobyl” radiation was only about one third of the average natural dose. This was the main factor responsible for the economic losses caused by the Chernobyl catastrophe, estimated to have reached $148 billion by 2000 for the Ukraine, and to reach $235
  • 19. . The Health Physics Society's position Statement first adopted in Jan. 1996, as revised in July 2010, states: In accordance with current knowledge of radiation risks, the Health Physics Society recommend against quantitative estimation of health risks below an individual dose of 5 rem(50 mSv) in one year or a lifetime dose of 10 rem (100 mSv) above that received from natural sources. . French Academy of Sciences and the National Academy of Medicine published a report in 2005 that rejected the LNT model in favour of a threshold dose response and a significantly reduced risk at low radiation exposures.
  • 20. What do we need to do? • Realistic worst case assessment in public domain at each site taking margins beyond design basis into account • Pragmatic evidence based intervention levels ( not biased by LNT) to be articulated in advance • Credibly demonstrate best estimate impact in public domain (expected to be much lower) • Develop and deploy systems that do not cause any adverse impact in public domain
  • 21. Thank you Visit www.anilkakodkar.in