Korea Atomic Energy Research Institute (KAERI) is in the process of carrying out a
Nuclear Hydrogen Development and Demonstration (NHDD) Program by considering the indirect
cycle gas cooled reactors that produce heat at temperatures in the order of 950°C. A coaxial doubletube
hot gas duct (HGD) is a key component connecting the reactor pressure vessel and the
intermediate heat exchanger (IHX) for the NHDD program. Recently, a preliminary design
evaluation for the hot gas duct of the NHDD program was carried out. These preliminary design
activities include a preliminary decision on the geometric dimensions, a preliminary strength
evaluation, an appropriate material selection, and identifying the design code for the HGD. In this
study, a preliminary strength evaluation for the HGD of the NHDD program has been undertaken
based on the HTR-10 design concepts. Also, a preliminary evaluation of the creep-fatigue damage
for a high temperature HGD structure has been carried out according to the draft code case for
Alloy 617. Preliminary strength evaluation results for the HGD showed that the geometric
dimensions of the proposed HGD would be acceptable for the design requirements.