원자력 수소 생산용 공정열교환기 모델의 고온설계 및 손상 평가

The generation of hydrogen using nuclear energy has become a viable means in producing an emission-free energy. A process heat exchanger (PHE) transfers the heat generated from a nuclear hydrogen reactor to a sulfur-iodine hydrogen production system in the NHDD (Nuclear Hydrogen Development and Demonstration). The inlet temperature in the primary side of the PHE mockup in this study is 950℃ with an internal pressure of 7MPa while the inlet temperature in the secondary side of the PHE is 500℃ with internal pressure of 4MPa. An evaluation of creep-fatigue damage on the PHE mockup has been carried out from finite element analysis with the full three dimensional model of the PHE. The candidate materials of the PHE are Alloy 617 and Hastelloy X. In this study, Alloy 617 was considered as PHE material because a very high temperature design guideline is currently available only for Alloy 617 as ASME draft code case. Based on the 3D finite element analysis on the PHE model, creep-fatigue damage evaluation at very high temperature was carried out according to the ASME Draft Code Case for Alloy 617.