Summary of the experimental multi-purpose very high temperature gas cooled reactor design

In 1969 JAERI started the design study of the Experimental Multi-purpose Very High Temperature Gas Cooled Reactor (the Experimental VHTR), and trial design, preliminary design, conceptual design, comprehensive system design and the first and second stage of detailed design have been carried out. Hereafter JAERI is going to pursue the rationalized Experimental VHTR system which maintains the required functions and performance and has the potential for reducing the construction cost, utilizing extensively the inherent safety features of HTGRs. In the current design, i.e. the second stage of detailed design, the reactor outlet coolant temperature is 9500C to aim earlier construction of the Experimental VHTR, according to the specification in ''Long-term plan for the development and utilization of nuclear energy'' revised by Japan Atomic Energy Commission in June 1982. This report presents the results based mainly on the comprehensive system design (completed by 1980.3) which is the last overall system design of the Experimental VHTR aiming 10000C reactor outlet coolant temperature and partially on the first stage (completed by 1981.3) of detailed design in the form of ''an application of reactor construction permit, Appendix 8'', excepting comformance with ''Safety Design Requirements'' which correspond to ''Safety Design Criteria for Water Cooled Nuclear Power Plants issued by Japan Nuclear Safety Commission''. (author)