Validation of computer code 'ATMIKA' against RD-14m small break LOCA experiments

The simulation of Small Break Loss-of-Coolant Accident (SBLOCA) experiments in the RD-14M integral test facility is performed under the auspices of International Atomic Energy Agency (IAEA) as an International Collaborative Standard Problem (ICSP) with the objective to benchmark and validate the in-house developed system thermal-hydraulic neutronic computer code 'ATMIKA', extensively used to analyze postulated events in Indian PHWRs. RD-14M is an 11 MW, full-elevation-scaled extensively instrumented thermal hydraulic Canadian test facility, possessing most of the key components of a CANDU (CANada Deuterium Uranium) primary heat transport system (PHTS). The loop configuration is similar to figure of-eight geometry of a typical CANDU circuit and it is intended to reproduce the important geometric features of a reactor PHTS and the appropriate operating conditions. 'ATMIKA' prediction and its comparison against SBLOCA experimental results are compared in this paper. A specific SBLOCA experiment 'B9006' is selected for the Computer code 'ATMIKA' predictions