Abstract
Japan Atomic Energy Research Institute has been constructing a 30-MWt HTGR, named HTTR, to develop technology and to demonstrate effectiveness of high-temperature nuclear heat utilization. A hydrogen production system by natural gas steam reforming is to be the first heat utilization system of the HTTR. This report describes an out-of-pile demonstration tests program required for hydrogen production system coupling with the HTTR. The demonstration tests are classified into three parts as follows; (1) an out-of-pile hydrogen production test to develop operational and control technologies and to demonstrate high-temperature components such as a steam reformer and so on under simulated operational conditions, (2) a material test of catalyst tube, which is the pressure boundary between coolant (helium gas) and process gases, to estimate the effect of corrosion and hydrogen embrittlement on material strength (Hastelloy XR), and (3) a hydrogen permeation test to estimate tritium transportation from reactor to produced hydrogen. As for the out-of-pile hydrogen production test, a 1/30-scale test equipment which simulates key components downstream from an intermediate heat exchanger of the HTTR is under construction aiming at completion in 2000. The catalyst tube material and hydrogen permeation tests have started and are to be continued to 2000.
