Page 115 - AERB Annual Report 2020
P. 115

Fig.7.3 (a): Heat Generating Volume and         Fig. 7.3 (b): Temperature Field with Air Gap
                              Schematic of Source Pins                     of 5mm at the Coil & Concrete
                                                                           Interface in last leg (NDC)

                  7.2  SEVERE ACCIDENT STUDIES                 analysis, the moderator inside the Calandria was
                                                               not considered. A detailed 3D unstructured mesh
                  7.2.1    CFD Analysis for Estimation of Calandria   geometric  model  considering  all  the  reactor
                        temperature  under  Severe  Accident   channels and calandria was developed (as shown
                        Conditions                             in  Fig.  7.4  (a),  (b)  and  (c)).    The  temperature
                                                               evolution of calandria with time was estimated
                      During postulated severe accident scenario,   along  with  the  time  available  for  operator
                  the radiation heat transfer plays a very important   intervention  to  take  corrective  actions.  This
                  role. It is to be noted that radiation heat transfer   analysis provided more realistic picture in case of
                  cannot be modelled effectively in system thermal   Severe  Accident  where  radiation  heat  transfer
                  hydraulics codes like RELAP5 used to simulate   plays  signicant  role  and  the  time  durations
                  the postulated accident sequence. To overcome   available  for  operator  to  take  Severe  Accident
                  this  limitation,  Computational  Fluid  Dynamics   Analysis  &  Management  Guidelines  (SAMG)
                  (CFD)  analysis  using  ANSYS-Work  Bench  was   actions are estimated. The insights obtained are
                  performed  to  estimate  the  temperature    useful with respect to SAMG actions also.
                  distribution  in  PT-CT  and  calandria.  In  the


















                     Fig. 7.4: (a) Front and (b) Side view of Mesh of Channels,   Fig.7.4 (c): Closer view
                               Calandria & Calandria Vault                                       of Mesh

                  7.2.2      3D  CFD  Analysis  for  Hydrogen   internal  structures  and  wall  thickness  were
                          Distribution  in  700  MWe  PHWR     included in this mesh. The in-house developed
                          Containment                          wall  steam  condensation  model  was  utilized
                                                               through  the  user-dened  functions  (UDF).  The
                      The objective is to determine the distribution   simulation  has  been  divided  into  three  phases,
                 of hydrogen in the containment in the presence of   LOCA phase (0-100 s), Hydrogen release phase
                 condensing steam environment without crediting   before OPRD rupture (100-800 s) and Moderator
                 hydrogen recombiners. A full 3D structured mesh   boil-off phase (800-36000 s). The simulation was
                 for  the  entire  containment  was  generated.  The   performed up to 40,000 s (11.1 hrs).


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