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During the past year we continued to serve as a peer reviewer of small modular reactor designs being developed by GA and GE with balance-of-plant layouts being developed by Bechtel Group, Inc. They are also performing extensive testing of aggregate materials obtained from potential HTR site areas for possible use in prestressed concrete reactor vessels.
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Researchers at ORNL are developing welding techniques for attaching steam generator tubing to the tubesheets and are testing ceramic pads on which the core posts rest. This evaluation is being performed at the ORNL Tower Shielding Facility. Other work includes experimental evaluation of the shielding effectiveness of the lower portions of an HTR core. Our work in component development and testing centers in the Component more » Flow Test Loop (CFTL), which is being used to evaluate the performance of the HTR core support structure.
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We are also developing improved reactor physics design methods. The ORNL has an important role in the development of improved HTR graphites and in the specification of criteria that need to be met by commercial products. Our studies are also providing basic data on the mechanical, physical, and chemical behavior of HTR materials, including metals, ceramics, graphite, and concrete. In the HTR fuels area, we are providing detailed statistical information on the fission product retention performance of irradiated fuel. ORNL continues to make significant contributions to the national program. Original copy available until stock is exhausted Country of Publication: United States Language: English Subject: 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 Authors: Kasten, P R Rittenhouse, P L Bartine, D E Sanders, J P Publication Date: Research Org.: Oak Ridge National Lab., TN (USA) OSTI Identifier: 6174841 Report Number(s): ORNL-5960 ON: DE83013725 DOE Contract Number: W-7405-ENG-26 Resource Type: Technical Report Resource Relation: Other Information: Portions are illegible in microfiche products.