The high-temperature gas-cooling reactor (HTGR) is an advanced converter reactor operated by using thorium/uranium cycle and utilizing 93% 235U-enriched or 20% 235U-enriched uranium and thorium as fissile fuel. In this paper
two fuel cycles of the HTGR
i. e. once-through and recycle
have been investigated. The early stage costs of fuel and fuel cycle were calculated. Effects of natural uranium
enrichment
reprocessing and fabrication of the Th-U recycle fuel on price variation were studied.
Development and Verification of Transient Analysis Code of Helical Coil Steam Generator of High-Temperature Gas-Cooled Reactor Based on All-Implicit Algorithm
Related Author
LIU Wei1 HU Shouyin1 XU Liang2 TANG Tinghui2 WANG Lang1 WU Pan2 SHAN Jianqiang2
Related Institution
(Huaneng Nuclear Energy Technology Institute, China Huaneng Group Co., Ltd., Shanghai 200126, China)2(Xi’an Jiaotong University,,)