Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Studies of HTGR Th-U fuel cycle at the Institute of Nuclear Energy Technology, Tsinghua University

Zhu Yongjin (Tsinghua Univ., Beijing (China). Inst. of Nuclear Energy Technology)

Abstract

In the 1980s, thorium-uranium fuel cycle with high temperature gas cooled reactors (HTGR) was studied and the results are summarized in the present paper.

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key words: Fast Neutron Spectrum Systems, Nuclear Technology
Reference:
Advanced fuels with reduced actinide generation.Technical committee meeting, Vienna (Austria). 21-23 Nov 1995
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--916, pp:171-177