干旱区生态环境知识资源中心(Arid): High-temperature gas-cooled reactor technology development program. Annual progress report for period ending December 31, 1982

Arid

DOI	10.2172/6174841
报告编号	ORNL-5960
来源ID	OSTI_ID: 6174841
	High-temperature gas-cooled reactor technology development program. Annual progress report for period ending December 31, 1982
	Kasten, P.R.; Rittenhouse, P.L.; Bartine, D.E.; Sanders, J.P.
英文摘要	During 1982 the High-Temperature Gas-Cooled Reactor (HTGR) Technology Program at Oak Ridge National Laboratory (ORNL) continued to develop experimental data required for the design and licensing of cogeneration HTGRs. The program involves fuels and materials development (including metals, graphite, ceramic, and concrete materials), HTGR chemistry studies, structural component development and testing, reactor physics and shielding studies, performance testing of the reactor core support structure, and HTGR application and evaluation studies.
出版年	1983
报告类型	Technical Report
语种	英语
国家	美国
来源学科分类	21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS ; 36 MATERIALS SCIENCE ; CHROMIUM-MOLYBDENUM STEELS ; MECHANICAL PROPERTIES ; CONCRETES ; GRAPHITE ; PHYSICAL RADIATION EFFECTS ; HASTELLOY X ; HTGR TYPE REACTORS ; REACTOR MATERIALS ; INCONEL 617 ; RESEARCH PROGRAMS ; SILICON CARBIDES ; URANIUM CARBIDES ; URANIUM DIOXIDE ; CORROSION ; PRIMARY COOLANT CIRCUITS ; SHIELDING ; TEST FACILITIES ; ACTINIDE COMPOUNDS ; ALLOYS ; ALUMINIUM ALLOYS ; BUILDING MATERIALS ; CARBIDES ; CARBON ; CARBON COMPOUNDS ; CHALCOGENIDES ; CHEMICAL REACTIONS ; CHROMIUM ALLOYS ; CHROMIUM STEELS ; COBALT ALLOYS ; COOLING SYSTEMS ; ELEMENTAL MINERALS ; ELEMENTS ; ENERGY SYSTEMS ; GAS COOLED REACTORS ; GRAPHITE MODERATED REACTORS ; HASTELLOYS ; HEAT RESISTANT MATERIALS ; HEAT RESISTING ALLOYS ; INCONEL ALLOYS ; IRON ALLOYS ; IRON BASE ALLOYS ; MATERIALS ; MINERALS ; MOLYBDENUM ALLOYS ; NICKEL ALLOYS ; NICKEL BASE ALLOYS ; NONMETALS ; OXIDES ; OXYGEN COMPOUNDS ; RADIATION EFFECTS ; REACTOR COMPONENTS ; REACTOR COOLING SYSTEMS ; REACTORS ; SILICON COMPOUNDS ; STEELS ; TUNGSTEN ALLOYS ; URANIUM COMPOUNDS ; URANIUM OXIDES 210300* -- Power Reactors, Nonbreeding, Graphite Moderated ; 360603 -- Materials-- Properties ; 360206 -- Ceramics, Cermets, & Refractories-- Radiation Effects ; 360603 -- Materials-- Properties
URL	http://www.osti.gov/scitech/servlets/purl/6174841
资源类型	科技报告
条目标识符	http://119.78.100.177/qdio/handle/2XILL650/263475
推荐引用方式 GB/T 7714	Kasten, P.R.,Rittenhouse, P.L.,Bartine, D.E.,et al. High-temperature gas-cooled reactor technology development program. Annual progress report for period ending December 31, 1982,1983.