THE ORNL GAS-COOLED REACTOR. PART I. SUMMARY REPORT. PARTS 2, 3, AND 4. PLANT DESIGN

Technical Report · Tue Apr 01 04:00:00 EST 1958

OSTI ID:4331143

These four parts were issued separately, but are cataloged as a unit. A conceptual design is given for a helium cooled, graphite moderated reactor using enriched UO/sub 2/ fuel in stainless steel capsules. This study is based on existing technology. The reactor is designed to produce a gross thermal power output of 687 Mw. The net electrical power output of the design specification for such a plant should be 1000 deg F gas temperature. Part II contains detailed information on gascooled reactor physics, materials, fuel elements, and the reactor. Part III deals with the details of the gas system, instrumentation and controls, operating procedures, and the steam system. Part IV gives the proposed plant design, the cost analysis, heat transfer performance, the reactor support and charging machine, fuel element cost data, and design data for British and U. S. gas-cooled reactors. (M.H.R.)

• Research Organization: Oak Ridge National Lab., Tenn.
• DOE Contract Number: W-7405-ENG-26
• NSA Number: NSA-12-008737
• OSTI ID: 4331143
• Report Number(s): ORNL-2500(Pts. 1-4)
• Country of Publication: United States
• Language: English

Related Subjects

CANNING-- CONTROL-- ELECTRICITY-- ENRICHMENT-- FUEL ELEMENTS-- GAS COOLANT-- GAS FLOW-- GASES-- GRAPHITE MODERATOR-- HELIUM-- INSTRUMENTS-- OPERATION-- ORNL-- PLANNING-- POWER-- POWER PLANTS-- PRODUCTION-- REACTORS-- STAINLESS STEELS-- STEAM-- URANIUM DIOXIDE
CANNING-- ECONOMICS-- ELECTRICITY-- ENRICHMENT-- FUEL ELEMENTS-- GAS COOLANT-- GRAPHITE MODERATOR-- HEAT TRANSFER-- HELIUM-- ORNL-- PLANNING-- POWER-- POWER PLANTS-- PRODUCTION-- REACTOR FUELING-- REACTORS-- STAINLESS STEELS-- UNITED KINGDOM-- URANIUM DIOXIDE-- USA
CANNING-- ELECTRICITY-- ENRICHMENT-- FUEL ELEMENTS-- GAS COOLANT-- GRAPHITE MODERATOR-- HELIUM-- ORNL-- PLANNING-- POWER--
PHYSICS