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AbstractAbstract
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p. 773-783; 1973; American Society of Mechanical Engineers; New York; 2. international congress for pressure vessel and piping technology; San Antonio, Texas, USA; 1 Oct 1973
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Book
Literature Type
Conference
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Udoguchi, T.; Asada, Y.; Ichino, I.
Creep and fatigue in elevated temperature applications. International conference sponsored by the Institution of Mechanical Engineers, American Society of Mechanical Engineers, American Society for Testing Materials, Philadelphia, 23-27 September 1973 and Sheffield, 1-5 April 1974. Vol. 11975
Creep and fatigue in elevated temperature applications. International conference sponsored by the Institution of Mechanical Engineers, American Society of Mechanical Engineers, American Society for Testing Materials, Philadelphia, 23-27 September 1973 and Sheffield, 1-5 April 1974. Vol. 11975
AbstractAbstract
[en] The effect of frequency or hold-time on the low-cycle fatigue strength of AISI 316 stainless steel and SCM 3 Cr-Mo steel for fuel cladding, piping and other structural members of LMFBR is investigated under high temperature conditions. Push-pull fatigue tests are conducted in air under conditions of fully reversed axial strain-control with a tensile strain hold-time ranging from 0 to 120 min for AISI 316, and with a tensile and an equal compressive strain hold-time ranging from 0 to 995 s for SCM 3. In these tests, a considerable decrease of fatigue life is observed as the hold-time is increased. An empirical formula is presented which can predict well the effect of hold-time on high temperature low-cycle fatigue life in terms of frequency. The formula is a little different from those in the literature. (author)
Primary Subject
Source
Institution of Mechanical Engineers, London (UK); p. 211.1-211.9; ISBN 0852983042; ; 1975; Mechanical Engineering Pubs; London; International conference on creep and fatigue in elevated temperature applications; Philadelphia, USA; 23 Sep 1973
Record Type
Book
Literature Type
Conference
Country of publication
ALLOYS, BREEDER REACTORS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, HEAT RESISTING ALLOYS, IRON ALLOYS, IRON BASE ALLOYS, LIQUID METAL COOLED REACTORS, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, NICKEL ALLOYS, REACTORS, STAINLESS STEELS, STEELS, TRANSITION ELEMENT ALLOYS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Udoguchi, T.; Asada, Y.; Ichino, I.
Creep and fatigue in elevated temperature applications. Volume I1975
Creep and fatigue in elevated temperature applications. Volume I1975
AbstractAbstract
[en] The effect of frequency or hold-time on the low-cycle fatigue strength of AISI 316 stainless steel and SCM 3 Cr--Mo steel for fuel cladding, piping, and other structural members of LMFBR is investigated under high temperature conditions. Push-pull fatigue tests are conducted in air under conditions of fully reversed axial strain-control with a tensile strain hold-time ranging fromm 0 to 120 min for AISI 316, and with a tensile and an equal compressive strain hold-time ranging from 0 to 995 s for SCM 3. In these tests, a decrease of fatigue life is observed as the hold-time is increased. An empirical formula is presented which can predict well the effect of hold-time on high temperature low-cycle fatigue life in terms of frequency. The formula is a little different from those in the literature
Primary Subject
Secondary Subject
Source
Anon; p. 211.1-211.9; 1975; Mechanical Engineering Publications; New York; International conference on creep and fatigue in elevated temperature applications; Philadelphia, Pennsylvania, USA; 23 Sep 1973
Record Type
Book
Literature Type
Conference
Country of publication
ALLOYS, BREEDER REACTORS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, EPITHERMAL REACTORS, FAST REACTORS, FATIGUE, FBR TYPE REACTORS, HEAT RESISTING ALLOYS, IRON ALLOYS, IRON BASE ALLOYS, LIQUID METAL COOLED REACTORS, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, NICKEL ALLOYS, REACTORS, STAINLESS STEELS, STEELS, TRANSITION ELEMENT ALLOYS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Research and development work done recently in connection with high temperature projects in Japan are briefly reviewed. The subjects discussed are: development of high temperature resisting superalloys; creep rupture strength of welded joints; environmental effects on materials in elevated temperature service; effect of cold work on creep strength; elastic follow-up; criterion for high temperature allowable stress; and estimation of creep damage. (author)
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Record Type
Journal Article
Journal
Proceedings of the Institution of Mechanical Engineers; ISSN 0020-3483; ; v. 194 p. 391-402
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INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A study was made to develop a method for evaluation of the local strain in a cladding tube of the Advanced Thermal Reactor due to radial cracking of a UO2 fuel pellet. Effects of the number of cracks, initial crack width and the friction coefficient of a pellet-clad interface on behaviors of the local strain in a cladding tube were evaluated with a modelized experiment. A Zircaloy-2 ring specimen with inner diameter of 95 mm, height of 25 mm and wall thickness of 5 mm was expanded at room temperature with equally divided peripheral dice of a tool steel set in a specimen. The dice were divided into 8, 12 or 16 pieces. For each dividing number, two dice edge geometries were prepared, that is, not chamfered and chamfered by 2 mm. Strains of an external surface of the specimen were measured with 28 wire strain gages with gage length of 0.3 mm. The friction coefficient on the pellet-clad contact surface was not measured, but two friction conditions were prepared. One was metal-metal contact and the other was a contact surface coated with teflon film. The estimated friction coefficient was 0.1 for the former and 0.05 for the latter. An elastic-plastic analysis was carried out in order to evaluate the membrane hoop strain in the cladding tube. The analysis was made under two conditions. One was a plane stress condition of a radial and hoop stress which resembled the state of stress-strain developed in the ring specimen. The other was a plane strain condition of a radial and hoop strain which approximated the stress-strain state in a cladding tube
Primary Subject
Source
v. C; 1977; C 2/3, 9 p; 4. International conference on structural mechanics in reactor technology; San Francisco, Calif., USA; 15 - 19 Aug 1977
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
ACTINIDE COMPOUNDS, ALLOYS, CHALCOGENIDES, CHROMIUM ADDITIONS, HEAVY WATER MODERATED REACTORS, HWLWR TYPE REACTORS, IRON ADDITIONS, MECHANICAL PROPERTIES, NATURAL URANIUM REACTORS, OXIDES, OXYGEN COMPOUNDS, PLUTONIUM REACTORS, POWER REACTORS, PRESSURE TUBE REACTORS, REACTORS, SYSTEMS ANALYSIS, TENSILE PROPERTIES, THERMAL REACTORS, TIN ALLOYS, TRANSITION ELEMENT ALLOYS, URANIUM COMPOUNDS, URANIUM OXIDES, WATER COOLED REACTORS, ZIRCALOY, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Steady and cyclic creep tests with internal pressure were performed at temperatures of 800 to 10000C on Hastelloy X cylinders with and without a circumferential Tungsten Inert Gas (TIG) welding technique. The creep rupture strength of the TIG welded cylinders was much lower than that of the non-welded cylinders whilst creep rupture strength reduction by the TIG technique was not observed in uniaxial creep tests. The reason for the low creep strength of welded cylinders is discussed and it is noted that the creep ductility of weld metal plays an essentially important role. In order to improve the creep strength of the TIG welded cylinder, various welding procedures with assorted weld metals were investigated. Some improvements were obtained by using welding techniques which had either Incoloy 800 or a modified Hastelloy X material as the filler metal. (U.K.)
Primary Subject
Record Type
Journal Article
Journal
International Journal of Pressure Vessels and Piping; ISSN 0308-0161; ; v. 9(2); p. 107-123
Country of publication
ALLOYS, CHROMIUM ALLOYS, COBALT ALLOYS, FAILURES, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HASTELLOYS, HEAT RESISTING ALLOYS, INCOLOY ALLOYS, IRON ALLOYS, IRON BASE ALLOYS, JOINTS, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, NICKEL ALLOYS, REACTORS, TENSILE PROPERTIES, TRANSITION ELEMENT ALLOYS, TUNGSTEN ALLOYS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Udoguchi, T.; Asada, Y.; Nakanishi, T.
Structural mechanics in reactor technology. Transactions. Vol. L1979
Structural mechanics in reactor technology. Transactions. Vol. L1979
AbstractAbstract
[en] In order to improve the creep strength of the TIG welded cylinder, welding procedure with miscellaneous weld metals was investigated. An improvement was obtained by Incoloy 800 and the modified-Hastelloy X as the filler metal. The creep rupture strength and ductility of the welded cylinders with these filler metals became higher to a certain extent than that of the conventional TIG welded cylinder. As another attempt to the improvement, electron beam welding was applied to the Hastelloy X cylinder. The result was so good that the creep rupture strength and ductility at 10000C were almost equal to those of the non-welded cylinder. (orig.)
Primary Subject
Source
Jaeger, T.A.; Boley, B.A. (eds.); Commission of the European Communities, Brussels (Belgium); Bundesanstalt fuer Materialpruefung, Berlin (Germany, F.R.); International Association for Structural Mechanics in Reactor Technology; p. L13/10; ISBN 0444 85367 7; ; 1979; p. L13/10; North-Holland Publishing Co; Amsterdam, Netherlands; 5. international conference on structural mechanics in reactor technology (SMIRT-5). 9. international seminar and 2. international seminar on structural reliability of mechanical components and subassemblies of nuclear power plants and 2. international seminar on containment of fast breeder reactors (CONFABRE-2); Berlin, Germany, F.R; 9 - 21 Aug 1979; INKA-CONF--79-321-549
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Udoguchi, T.; Ohsaki, Y.; Shibata, H.
Peaceful uses of atomic energy. Proceedings of the fourth international conference, jointly sponsored by the UN and the IAEA and held in Geneva, 6-16 September 1971. Vol. 31972
Peaceful uses of atomic energy. Proceedings of the fourth international conference, jointly sponsored by the UN and the IAEA and held in Geneva, 6-16 September 1971. Vol. 31972
AbstractAbstract
No abstract available
Primary Subject
Secondary Subject
Source
United Nations, New York (USA); International Atomic Energy Agency, Vienna (Austria); Proceedings series; 15 v.; v. 3 p. 297-308; 1972; IAEA/UN; Vienna; 4. international conference on the peaceful uses of atomic energy; Geneva, Switzerland; 6 Sep 1971; A/CONF.49/P--226; Microfiche of preprint available from INIS Clearinghouse.
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A study was made to develop a method for evaluation of the local strain in a cladding tube of the Advanced Thermal Reactor due to radial cracking to a UO2 fuel pellet. Effects of the number of cracks, initial crack width and the friction coefficient of a pellet-clad interface on behaviors of the local strain in a cladding tube were evaluated with a modelized experiment. Analytical evaluation of a membrane strain was also carried out on the basis of a procedure similar to that proposed by J. H. Gittus, Nuclear Engineering and Design 18 (1972) 69-82, in order to follow the experimental results and to extend the model experiment to cladding tube. A Zircaloy-2 ring specimen with inner diameter of 95 mm, height of 25 mm and wall thickness of 5 mm was expanded at room temperature with equally divided peripheral dice of a tool steel set in a specimen. Strains on an external surface of the specimen were measured with 28 wire strain gages with gage length of 0.3 mm. An elastic-plastic analysis was carried out in order to evaluate the membrane hoop strain in the cladding tube on the basis of a simple procedure similar to that proposed by Gittus. The results of analysis showed that the maximum hoop strain occured at a location apart from the dice edge. This was caused by unloading in the crack opening portion. The strain concentration factor obtained from analysis is greater than that obtained from experiment. The difference of concentration factors between analysis and experiment is due to the bending strain. Therefore, the strain concentration factor at the inner surface is evaluated from the experimental concentration factor at the external surface and the analytical concentration factor of a membrane strain. (Auth.)
Primary Subject
Source
Jaeger, T.A.; Boley, B.A. (eds.); International Association for Structural Mechanics in Reactor Technology; Commission of the European Communities, Brussels (Belgium); v. C p. C2/3 1-9; ISBN 0 444 85062 7; ; 1977; v. C p. C2/3 1-9; North-Holland; Amsterdam, Netherlands; 4. international conference on structural mechanics in reactor technology; San Francisco, USA; 15 - 19 Aug 1977
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Development of analytical procedure for the design of 1.5 Mwt helium gas intermediate heat exchanger
Hamanaka, J.; Kitagawa, M.; Goto, T.; Saiga, Y.; Yamada, Y.
Structural mechanics in reactor technology. Transactions. Vol. F1979
Structural mechanics in reactor technology. Transactions. Vol. F1979
AbstractAbstract
[en] This paper reports the structural integrity study of 1.5 Mwt helium gas intermediate heat exchanger performed as a part of 'Research and Development of Direct Steel Making Technology Utilizing High Temperature Reducing Gas' which is one of the National Research and Development Programs by Agency of Industrial Science and Technology, Ministry of International Trade and Industry, Japan. The normal operation temperature of the heat exchanger exceeds 10000C which is beyond the scope covered by the existing design code, e.g. ASME Code Case 1592. Therefore, a special analytical and experimental procedure should be developed to establish design rules of unprecedented components operating at extremely high temperature. (orig.)
Primary Subject
Secondary Subject
Source
Jaeger, T.A.; Boley, B.A. (eds.); Commission of the European Communities, Brussels (Belgium); Bundesanstalt fuer Materialpruefung, Berlin (Germany, F.R.); International Association for Structural Mechanics in Reactor Technology; p. F9/2 (1-10); ISBN 0444 85362 6; ; 1979; p. F9/2 (1-10); North-Holland Publishing Co; Amsterdam, Netherlands; 5. international conference on structural mechanics in reactor technology (SMIRT-5). 9. international seminar and 2. international seminar on structural reliability of mechanical components and subassemblies of nuclear power plants and 2. international seminar on containment of fast breeder reactors (CONFABRE-2); Berlin, Germany, F.R; 9 - 21 Aug 1979; INKA-CONF--79-321-232
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
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