This paper focuses on developing design methodologies that can quickly generate pre-conceptual design of battery reactor by means of first principle calculations, starting from core region to reactor vessel assembly and power conversion system. First, given the core composition and weight fraction data, the MCNP code is run to generate a neutron flux spectrum for homogenized geometry that is used with the available cross section data to generate the single group constants for neutron diffusion calculation. The bucklings of the critical core found from Neutronics Optimized Reactor Analysis (NORA) based on the diffusion equation are then compared against those obtained by trial and error utilizing the MCNP code over the range of design variables to generate a linear relationship used to adjust the buckling computed by the neutron diffusion equation. Next, key design parameters and constraints are chosen for the reactor vessel assembly considering technical specifications such as the thermal limits and manufacturing difficulties. Two objective functions are picked based on thermohydrodynamic and economic grounds. A first principle system code Optimized Supercritical Cycle Analysis (OSCA) is run to generate boundary conditions at heat exchanger interface with a view to optimizing the design of the supercritical fluid driven Brayton cycle. Selected design parameters are made available to the Momentum Integral Numerical Analysis (MINA) code to evaluate steady-state mass flow rate and coolant temperature distribution of the reactor vessel assembly. They are compared against the prescribed engineering constraints. The steps are repeated until an optimum value is obtained. The proposed methodology may help reduce the amount of computational effort required in initial stages of small reactor design. The resulting geometric information can be used as a starting point for detailed design procedure.

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