HTGR Knowledge Base

Conference Article: HTGR safety philosophy

Joksimovic, V.; Fisher, C.R. (General Atomic Co., San Diego, CA (USA))

Abstract

The accident at the Three Mile Island has focused public attention on reactor safety. Many public figures advocate a safer method of generating nuclear electricity for the second nuclear era in the U.S. The paper discusses the safety philosophy of a concept deemed suitable for this second nuclear era. The HTGR, in the course of its evolution, included safety as a significant determinant in design philosophy. This is particularly evident in the design features which provide inherent safety. Inherent features cause releases from a wide spectrum of accident conditions to be low. Engineered features supplement inherent features. The significance of HTGR safety features is quantified and order-of-magnitude type of comparisons are made with alternative ways of generating electricity.

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key words: after-heat removal; coated fuel particles; electric power; graphite; helium; htgr type reactors; natural convection; prestressed concrete; primary coolant circuits; reactor accidents; reactor cores; reactor safety; reactor vessels; refractories; safety engineering
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:207-213