Prediction of steady state behavior of AHWR by a coupled 3-D neutron kinetics and thermal hydraulic code

As a part of PROMISIN Code development the thermal hydraulic code RELAP 5 Mod 3.2 and 3-D neutron kinetics code ARCH have been coupled together. The coupled code has been used for prediction of the steady state behavior of the Advanced Heavy Water Reactor (AHWR). The two codes interact with each other by exchanging the properties. The convergence of the two codes is achieved exclusively and then they interact and exchange the properties which are changed during the run of the individual code The two codes interact with each other by exchanging the variable properties viz. Density to the ARCH code and power profile to the RELAP 5 code during steady state predictions. The simulation has been started with the uniform flux to the core i.e. there is no axial variation of the flux taken in the calculation. The density along the axial length of the core has been the input to the ARCH which in turn gives the flux profile of the core to REPLAP 5 based on the density feed back to the ARCH from the RELAP 5. Here in this paper the steady state of the AHWR is predicted by using the coupled neutronic thermal hydraulic code. Main Heat Transport System (MHTS) of the AHWR is modeled as lumped channel. (author)