Page 48 - AERB Bulletin English
P. 48

Regulatory Activities
          Safety Studies and Research Activities




                        Safety Studies and R&D Activities at SRI, Kalpakkam and Mumbai Headquarters

          AERB recognises the importance of Safety Analysis &   important  developmental  studies were taken up
          Research in support of its regulatory function. Safety   by AERB  and completed during this year.  Various
          analysis  and research activities are carried  out  by   studies were undertaken during 2019 in following
          AERB as a part of its regulatory activities.  Several   areas:






            THERMAL HYDRAULICS SAFETY STUDY                    SEVERE ACCIDENT            PROBABILISTIC
                                                               STUDIES                    SAFETY STUDIES
           In  support of regulatory review, number of studies on
           thermal hydraulics of nuclear and radiation facilities were
                                                               A number of studies on  A probabilistic safety
           undertaken.
                                                               severe  accident assessment  assessment  (PSA) of a
           •   A detailed 3-D transient heat transfer analysis  was   of nuclear  and  radiation  nuclear  and radiation
                                                               facilities were undertaken.    facility  provides  a
               carried  out  using COMSOL  for proposed  FBTR fast                        comprehensive    and
               flux  experimental  facility  (FFEF)  for  irradiation  of  •   Calculation  of Radiation  structured  approach
               radioactive samples.                                view Factor of 37 Pin Fuel  for identifying  failure
           •   Thermal transient analysis of CORAL high-level waste   Bundle  for estimation of  scenarios  and deriving
               raffinate  for  estimating  the  maximum  temperature   radiation view factors   numerical estimates of
               of  raffinate  waste  solution  during  unavailability  of   between  pins  of  bundle   the risks to workers and
                                                                                          members of the public.
               primary cooling water.                              and pin to  PT  (pressure
           •   Analyses  related to 700  MWe PHWR to evaluate the   tube).                The review of Shutdown
               effect of inadvertent opening of the Passive Decay Heat  •   Developed AERB  Source  and  Low  Power PSA
               Removal System valve during normal operation.       Term  Estimation Tool  report of MAPS-1&2 has
                                                                   for  KKNPP and MAPS  been completed.
           •   3-D model of concrete shield was developed in multi-
                                                                   reactors and  integrated
               physics  software COMSOL  for  Assessment  of  the
                                                                   with   the    in-house
               cooling coil capability in ISOMED.
                                                                   developed AERB tool.



                                                                                          AERB        continued
                                                                                          to    contribute   in
                                                                                          development        of
                                                                                          PRABHAVINI,      DAE
                                                                                          computer    code   to
                                                                                          address Design  Basis
                                                                                          Accidents  (DBA) and
                                                                                          Design      Extension
                                                                                          Conditions (DEC) in the
                                                                                          Indian nuclear reactors.





           Temperature Field Slices with Modified Coil & Water Cooling















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                  AERB BULLETIN 2019
                  AERB BULLETIN 2019
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