Preliminary Structural Assessment of Printed Circuit Steam Generator Heat Exchanger for Sodium-Cooled Fast Reactor

The success of the next generation of nuclear reactor will depend in part upon the correct selection of high effectiveness and high integrity of heat exchanger. To reach the high mechanical integrity of printed circuit heat exchanger, a tight standard will be strongly needed. In this paper, ASME Boiler and Pressure Vessel Code (BPVC) section VIII will be the standard for micro channel mechanical construction. In the other hand, ASME BPVC section III division 5 will be handed as the criteria code to evaluate the compliance of proposed geometry. Preliminary study of structural integrity steam generator heat exchanger has been conducted. Calculation result shows that proposed geometry can comply with ASME BPV code section III division 5. Allowable stress intensity (S_mt) can predict 3 x 10⁵ hours of lifetime operating service. FEA simulation using COMSOL Multiphysics indicate some "key-area" that should be highly considered for further study and design. Tip edge area of water channels are the highest area. Hence, it will be needed to give a strong concern in this area.