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AbstractAbstract
[en] The paper presents the results of the first mechanical test campaign performed on some members of a new family of stainless steels. Tensile and creep tests have been carried out in order to acquire the first indispensable information about the mechanical properties and the micro-structural thermodynamic stability of Ti plus Nb stabilized austenitic steels. A more comprehensive test campaign has been in progress since May 87. Optimized chemical compositions and higher Ni content alloys will be tested too. (author)
Primary Subject
Source
British Nuclear Energy Society, London; 454 p; ISBN 0 7277 1306 X; ; 1987; v. 1 p. 191-198; British Nuclear Energy Society; London (UK); International conference on materials for nuclear reactor core applications; Bristol (UK); 27-29 Oct 1987; Price Pound 60.00
Record Type
Book
Literature Type
Conference; Numerical Data
Country of publication
ALLOYS, BREEDER REACTORS, CARBON ADDITIONS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, CRYSTAL STRUCTURE, DATA, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, INFORMATION, IRON ALLOYS, IRON BASE ALLOYS, LIQUID METAL COOLED REACTORS, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, NUMERICAL DATA, REACTORS, STAINLESS STEELS, STEELS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Filacchioni, G.; Montanari, R.; Tata, M.E.; Pilloni, L., E-mail: gianni.filacchioni@casaccia.enea.it2002
AbstractAbstract
[en] Gas tungsten arc welding and electron beam welding methods were used to realise welding pools on plates of reduced activation martensitic steels. Structural and mechanical features of these simulated joints have been investigated in as-welded and post-welding heat-treated conditions. The research allowed to assess how each welding technique affects the original mechanical properties of materials and to find suitable post-welding heat treatments. This paper reports results from experimental activities on BATMAN II and F82H mod. steels carried out in the frame of the European Blanket Project - Structural Materials Program
Primary Subject
Secondary Subject
Source
S0022311502010735; Copyright (c) 2002 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Filacchioni, G.; De Angelis, U.; Ferrara, D.; Pilloni, L.
Fast reactor core and fuel structural behaviour1990
Fast reactor core and fuel structural behaviour1990
AbstractAbstract
[en] Irradiation with 1 MeV electrons had demonstrated the high swelling resistance of DS (double stabilized) steels. Experimental results from a first generation of 316 and 15Gr-15Ni (Ti + Nb) austenitic steels gave evidence of some drawbacks associated with an unoptimized chemical composition. A critical analysis led to a revised DS family and a second generation based on two principal steels: 15Gr-15Ni and 15Gr-25Ni. The higher Ni content alloy has been extensively characterized and the test programme for the lower Ni content alloy is well advanced. The mechanical and structural properties are promising for use in fast breeder reactor cores at high burn up. (author)
Primary Subject
Source
British Nuclear Energy Society, London (United Kingdom); 326 p; ISBN 0 7277 1566 6; ; 1990; p. 255-261; British Nuclear Energy Society; London (United Kingdom); International conference on fast reactor core and fuel structural behaviour; Inverness (United Kingdom); 4-6 Jun 1990
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Montanari, R.; Filacchioni, G.; Riccardi, B.; Tata, M.E.; Costanza, G., E-mail: roberto.montanari@uniroma2.it2004
AbstractAbstract
[en] Welded joints of 25-mm thick plates of Eurofer-97, produced by a multi-pass GTAW + filler material method, have been investigated before and after different heat treatments to identify the temperature-time combination that gives mechanical properties as close as possible to those of the base material. After NDE (non-destructive examinations), samples were annealed in the temperature range 730-750 deg. C for 1 and 2 h, microhardness was measured across the joints and FIMEC (flat-top cylinder indenter for mechanical characterization) tests were carried out in the molten zone (MZ), heat affected zone (HAZ) and in the matrix. The FIMEC method allowed determination on a local scale of the yield stress as obtained in standard tensile tests. Mechanical tests were supplemented by optical microscopy observations. The best results were obtained by the treatment at 750 deg. C for 2 h: original characteristics are substantially recovered in the HAZ but not completely in the MZ
Primary Subject
Source
ICFRM-11: 11. International conference on fusion reactor materials; Kyoto (Japan); 7-12 Dec 2003; S0022311504003204; Copyright (c) 2004 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Literature Type
Conference
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
External URLExternal URL
AbstractAbstract
No abstract available
Primary Subject
Source
Joint meeting of the American Nuclear Society and the Atomic Industrial Forum and Nuclear Energy Exhibition; San Francisco, California, USA; 11 Nov 1973; See CONF-731101-- Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Trans. Amer. Nucl. Soc; v. 17 p. 166
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Secondary Subject
Source
Joint meeting of the American Nuclear Society and the Atomic Industrial Forum and Nuclear Energy Exhibition; San Francisco, California, USA; 11 Nov 1973; See CONF-731101-- Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Trans. Amer. Nucl. Soc; v. 17 p. 172-173
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Secondary Subject
Source
19. annual meeting of the American Nuclear Society; Chicago, Illinois, USA; 10 Jun 1973; See CONF-730611-- Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Trans. Amer. Nucl. Soc; v. 16 p. 119-120
Country of publication
ACTINIDE COMPOUNDS, ALLOYS, CHALCOGENIDES, CHROMIUM ADDITIONS, CHROMIUM ALLOYS, DIMENSIONS, FUEL ELEMENTS, IRON ADDITIONS, IRON ALLOYS, OXIDES, PHYSICAL PROPERTIES, PLUTONIUM COMPOUNDS, RADIATION EFFECTS, REACTOR COMPONENTS, THERMODYNAMIC PROPERTIES, TIN ALLOYS, TRANSURANIUM COMPOUNDS, URANIUM COMPOUNDS, URANIUM OXIDES, ZIRCALOY, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Filacchioni, G.; Casagrande, E.; De Angelis, U.; De Santis, G.; Ferrara, D., E-mail: gianni.filacchioni@mail.casaccia.enea.it2002
AbstractAbstract
[en] In the present work, we have studied the strain rate sensitivity of tensile properties of TZM and Mo-5%Re alloys. Tests were performed at room temperature and around the transition temperature of each alloy, at strain rates varying over five decades. Ductility appeared insensitive to strain rate, whereas the strength is found to be strain rate dependent. Both proof stress and ultimate tensile strength are affected by strain rate and the Mo-5%Re alloy is more sensitive than TZM. As expected, the hardening decreases with temperature; in TZM alloy the strain rate sensitivity was apparent only at room temperature
Primary Subject
Source
S0022311502011911; Copyright (c) 2002 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Country of publication
ALLOY-MO99, ALLOYS, CORROSION RESISTANT ALLOYS, EVALUATION, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, MATERIALS, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, MOLYBDENUM BASE ALLOYS, PHYSICAL PROPERTIES, TENSILE PROPERTIES, THERMODYNAMIC PROPERTIES, TITANIUM ADDITIONS, TITANIUM ALLOYS, TRANSITION ELEMENT ALLOYS, ZIRCONIUM ADDITIONS, ZIRCONIUM ALLOYS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Record Type
Journal Article
Journal
Nuclear Technology; v. 21(3); p. 208-216
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
UO2-PuO2
Primary Subject
Source
European nuclear conference; Paris, France; 21 Apr 1975; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 20 p. 229-231
Country of publication
ACTINIDE COMPOUNDS, ALLOYS, CHALCOGENIDES, CHROMIUM ADDITIONS, FUEL ELEMENTS, IRON ADDITIONS, OXIDES, OXYGEN COMPOUNDS, PLUTONIUM COMPOUNDS, PLUTONIUM OXIDES, REACTOR COMPONENTS, TIN ALLOYS, TRANSITION ELEMENT ALLOYS, TRANSURANIUM COMPOUNDS, URANIUM COMPOUNDS, URANIUM OXIDES, ZIRCALOY, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
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