HTGR Knowledge Base

Conference Article: The reactor safety study of experimental multi-purpose VHTR design

Yasuno, T.; Mitake, S.; Ezaki, M.; Suzuki, K. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)

Abstract

Over the past years, the design works of the Experimental Very High Temperature Reactor (VHTR) plant have been conducted at Japan Atomic Energy Research Institute. The conceptual design has been completed and the more detailed design works and the safety analysis of the experimental VHTR plant are continued. The purposes of design studies are to show the feasibility of the experimental VHTR program, to specify the characteristics and functions of the plant components, to point out the R and D items necessary for the experimental VHTR plant construction, and to analyze the feature of the plant safety. In this paper the summary of system design and safety features of the experimental reactor are indicated. Main issues are the safety philosophy for the design basis accident, the accidents assumed and the engineered safety systems adopted in the design works.

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key words: diagrams; flowsheets; planning; reactor accidents; reactor components; reactor safety; specifications; vhtr reactor; accidents; enriched uranium reactors; experimental reactors; gas cooled reactors; graphite moderated reactors; helium cooled reactors; htgr type reactors; information; power reactors; reactors; research and test reactors; safety; thermal reactors
Reference:
International Atomic Energy Agency, Vienna (Austria). International Working Group on Gas-Cooled Reactors. Specialists meeting on gas-cooled reactor safety and licensing aspects, Lausanne, Switzerland, 1-3 September 1980. Summary report. Jan 1981
International Atomic Energy Agency, Vienna (Austria). International Working Group on High-Temperature Reactors.
IWGGCR--1, pp:198-207