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Gupta, Suneel K.; Mohta, Keshav; Singh, P.K.; Arora, Punit; Samal, M.K.; Syed, Ather; Chattopadhyay, J.
Bhabha Atomic Research Centre, Mumbai (India)2021
Bhabha Atomic Research Centre, Mumbai (India)2021
AbstractAbstract
[en] Austenitic and martensitic stainless steels find various applications in Indian nuclear reactors. Material properties such as tensile properties, creep deformation and stress-rupture behaviours, fatigue-fracture properties of several austenitic and martensitic stainless steels, used in Indian NPPs have been evaluated by RSD, BARC over a period of time for various requirements. These are compiled in the present volume that covers the following materials: (i) SS304L - High temperature tensile and creep-stress rupture properties of both base and weld material; fracture properties of base material; (ii) SS304LN - Tensile, fatigue, fracture and Fatigue Crack Growth Rate (FCGR) properties of both base and weld materials; (iii) SS403 - Tensile, fatigue, fracture, FCGR and impact properties; (iv) SS316LN - Tensile properties. (author)
Primary Subject
Source
Oct 2021; 83 p; 15 refs., 62 figs., 37 tabs.
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Report
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Country of publication
ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-MOLYBDENUM STEELS, CHROMIUM-NICKEL STEELS, CHROMIUM-NICKEL-MOLYBDENUM STEELS, CORROSION RESISTANT ALLOYS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, LOW CARBON-HIGH ALLOY STEELS, MARTENSITIC STEELS, MATERIALS, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, NICKEL ALLOYS, STAINLESS STEELS, STEEL-CR12, STEEL-CR17NI12MO3-L, STEEL-CR19NI10-L, STEELS, TRANSITION ELEMENT ALLOYS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Edwards, D.; Simonen, E.; Bruemmer, S.
13th International conference on environmental degradation of materials in nuclear power systems2007
13th International conference on environmental degradation of materials in nuclear power systems2007
AbstractAbstract
[en] A series of Bor60 fast-reactor irradiations have been completed on commercial and laboratory heats of 304LSS and 316SS irradiated at 320oC to doses from 5 to 25 dpa. Dose-dependent grain boundary composition changes are assessed for the 5 heats mapping radiation-induced segregation (RIS) of alloying and impurity elements. The strongest RIS response was observed in a high-purity, Si-doped, 304LSS laboratory heat, while a cold-worked 316SS commercial heat exhibited the lowest level of RIS response at a high dose. Results for the fast-reactor-irradiated materials were consistent at low doses with that measured in similar materials irradiated in light-water-reactor (LWR) environments. Stronger RIS was indicated for LWR versus fast-reactor irradiations at high doses, but more data is needed. In general, heat-to-heat differences revealed larger variations in RIS than differences between the two irradiation environments. (author)
Primary Subject
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); 388 Megabytes; ISBN 0-919784-89-5;
; 2007; [17 p.]; 13. International conference on environmental degradation of materials in nuclear power systems; Whistler, BC (Canada); 19-23 Aug 2007; Available from the Canadian Nuclear Society, Toronto, Ontario (Canada); 14 refs., 3 tabs., 14 figs.

Record Type
Miscellaneous
Literature Type
Conference
Country of publication
ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-MOLYBDENUM STEELS, CHROMIUM-NICKEL STEELS, CHROMIUM-NICKEL-MOLYBDENUM STEELS, CORROSION RESISTANT ALLOYS, FABRICATION, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, LOW CARBON-HIGH ALLOY STEELS, MATERIALS, MATERIALS WORKING, MICROSTRUCTURE, MOLYBDENUM ALLOYS, NICKEL ALLOYS, REACTORS, STAINLESS STEELS, STEEL-CR17NI12MO3, STEEL-CR17NI12MO3-L, STEEL-CR19NI10, STEEL-CR19NI10-L, STEELS, TRANSITION ELEMENT ALLOYS
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The microstructures of six material/fluence combinations of stainless steels retrieved from BWR components (top guide and control rods) have been examined by atom probe tomography; the irradiated microstructure had been already characterized by transmission electron microscopy (TEM). The fracture toughness of two material/fluence combinations had been previously measured. The aggregate results strongly suggest that radiation-induced clusters play a significant role in the degradation of fracture toughness that occurs at fluences below ∼ 13 dpa. Because TEM has not been able to consistently identify and quantify the nano-sized clusters in this fluence range, it has not highlighted the potential role of radiation-induced clusters. (authors)
Primary Subject
Source
2015; 35 p; Fontevraud 8: Conference on Contribution of Materials Investigations and Operating Experience to LWRs' Safety, Performance and Reliability; Avignon (France); 15-18 Sep 2014; 9 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-MOLYBDENUM STEELS, CHROMIUM-NICKEL STEELS, CHROMIUM-NICKEL-MOLYBDENUM STEELS, CORROSION RESISTANT ALLOYS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, LOW CARBON-HIGH ALLOY STEELS, MATERIALS, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, NICKEL ALLOYS, STAINLESS STEELS, STEEL-CR17NI12MO3-L, STEEL-CR19NI10, STEEL-CR19NI10-L, STEELS, TRANSITION ELEMENT ALLOYS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Barlak, M.; Piekoszewski, J.; Werner, Z.
International Conference on Development and Applications of Nuclear Technologies (NUTECH-2011). Book of Abstracts2011
International Conference on Development and Applications of Nuclear Technologies (NUTECH-2011). Book of Abstracts2011
AbstractAbstract
No abstract available
Primary Subject
Source
Dudala, J.; Stegowski, Z. (eds.); Faculty of Physics and Applied Computer Science, AGH Technical University, Cracow (Poland); [226 p.]; ISBN 978-83-925779-1-1;
; 2011; p. 66; NUTECH-2011: International Conference on Development and Applications of Nuclear Technologies; Krakow (Poland); 11-14 Sep 2011; Also available from the Faculty of Physics and Applied Computer Science, AGH University of Science and Technology, Cracow, Poland

Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
ALLOYS, AUSTENITIC STEELS, BEAMS, CARBON ADDITIONS, CHEMICAL REACTIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-MOLYBDENUM STEELS, CHROMIUM-NICKEL STEELS, CHROMIUM-NICKEL-MOLYBDENUM STEELS, CORROSION RESISTANT ALLOYS, CROLOY, FERRITIC STEELS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, MATERIALS, MOLYBDENUM ALLOYS, NICKEL ALLOYS, RARE EARTH ALLOYS, STAINLESS STEELS, STEEL-CR16, STEEL-CR17NI12MO3, STEEL-CR19NI10, STEELS, TRANSITION ELEMENT ALLOYS
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Morimoto, Akihiro, E-mail: morimoto@mech.kindai.ac.jp2006
AbstractAbstract
[en] The rotating bending fatigue tests were carried out at room temperature, 200degC, 400degC, 600degC and 800degC with a frequency of 1200 cycles/min. using SUS 304 solution treatment material and SUS 304-1/2H 10% cold working material, and were carried out at room temperature, 300degC and 600degC using SUS 430 and SUS 403. The cold working material showed higher strength at finite life and fatigue limit in every temperature than the other materials did, although the difference of fatigue limit above 400degC between the cold working material and the other materials were a little. The relationships between the fatigue limit σW and the tensile strength σB were obtained as σW=0.44σB for SUS 304 at every temperature and SUS 304-1/2 H over 200degC, and σW=0.58σB for SUS 430, SUS 403 at every temperature and SUS 304-1/2 H below 200degC. Besides, the relationship between the stress ratio σa/σωR.T. and the parameter P=(10 - log Nf)/T was proposed to estimate the fatigue strength at finite life, where σa is the bending stress amplitude, σωR.T. is the fatigue limit at room temperature, Nf is the cycles to failure and T is the absolute temperature. (author)
Primary Subject
Source
10 refs., 11 figs., 4 tabs.
Record Type
Journal Article
Journal
Nippon Kikai Gakkai Ronbunshu, A Hen; ISSN 0387-5008;
; v. 72(713); p. 114-119

Country of publication
ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, CROLOY, DEFORMATION, FABRICATION, FERRITIC STEELS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, MARTENSITIC STEELS, MATERIALS, MATERIALS WORKING, MECHANICAL PROPERTIES, MOTION, NICKEL ALLOYS, STAINLESS STEELS, STEEL-CR12, STEEL-CR16, STEEL-CR19NI10, STEELS, TEMPERATURE RANGE, TRANSITION ELEMENT ALLOYS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Acharya, Saikat; Bysakh, Sandip; Moitra, A.
Proceedings of the international conference on electron microscopy and allied techniques and thirty eighth annual meeting of the Electron Microscope Society of India: souvenir and book of abstracts2017
Proceedings of the international conference on electron microscopy and allied techniques and thirty eighth annual meeting of the Electron Microscope Society of India: souvenir and book of abstracts2017
AbstractAbstract
[en] Electron microscopy has provided immense scope to utilize the versatility of this technique for identification of various microstructural changes that occurs due to effect of high strain rates in austenitic steels. Thus, an attempt has been made using these techniques to understand the subtle microstructural changes that happen in the austenitic steels e.g., SS304L and SS316LN due to high strain rate compression effect which are very relevant to the various field applications e.g., defence, nuclear, aerospace etc. (author)
Primary Subject
Source
Electron Microscope Society of India (India); Indira Gandhi Centre for Atomic Research, Kalpakkam (India); Indian Institute of Technology Madras, Chennai (India); 511 p; 2017; p. 276; EMSI-2017: international conference on electron microscopy and allied techniques; Mahabalipuram (India); 17-19 Jul 2017; 38. annual meeting of the Electron Microscope Society of India; Mahabalipuram (India); 17-19 Jul 2017
Record Type
Book
Literature Type
Conference
Country of publication
ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-MOLYBDENUM STEELS, CHROMIUM-NICKEL STEELS, CHROMIUM-NICKEL-MOLYBDENUM STEELS, CORROSION RESISTANT ALLOYS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, LOW CARBON-HIGH ALLOY STEELS, MATERIALS, MICROSCOPY, MOLYBDENUM ALLOYS, NICKEL ALLOYS, STAINLESS STEELS, STEEL-CR17NI12MO3-L, STEEL-CR19NI10-L, STEELS, TRANSITION ELEMENT ALLOYS
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Tavassoli, A.A.; Picker, C.; Wareing, J.
Effects of radiation on materials: 17. international symposium1996
Effects of radiation on materials: 17. international symposium1996
AbstractAbstract
[en] Data on the influence of low dose 400--550 C irradiation on the mechanical properties of structural steels (Types 304, 316, 316L, 316H and 316L(N) and associated weld metals) at temperatures from 20 C to 750 C, have been compiled from published literature and the results of British, Dutch, French and German laboratories. Properties evaluated include tensile, impact, creep, fatigue, and creep-fatigue. The preliminary results, which cover the dose range from 0 to 5 displacements per atom (and/or up to 9 appm helium) are presented as comparisons between irradiated and unirradiated control data, covering a range of strength and cyclic properties. The results show that low dose irradiation can have a significant influence on the properties, i.e.: (1) increases in tensile proof strength; (2) reductions in tensile ductility; (3) decreases in impact energy; (4) reductions in creep-rupture strength and ductility; and (5) reductions in creep-fatigue endurance. By considering the influence of irradiation temperature and dose level, the results are rationalized in terms of irradiation hardening and grain boundary embrittlement mechanisms
Primary Subject
Source
Gelles, D.S. (ed.) (Pacific Northwest National Lab., Richland, WA (United States)); Nanstad, R.K. (ed.) (Oak Ridge National Lab., TN (United States)); Kumar, A.S. (ed.) (Univ. of Missouri, Rolla, MO (United States)); Little, E.A. (ed.) (University College of Swansea (United Kingdom)); ASTM special technical publication, 1270; [1175 p.]; ISBN 0-8031-2016-8;
; 1996; p. 995-1012; American Society for Testing and Materials; West Conshohocken, PA (United States); 17. symposium on effects of radiation on materials; Sun Valley, ID (United States); 20-23 Jun 1994; ISSN 1050-7515;
; ASTM, 100 Barr Harbor Drive, West Conshohocken, PA 19428-2959 (United States)


Record Type
Book
Literature Type
Conference
Country of publication
ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-MOLYBDENUM STEELS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, LOW CARBON-HIGH ALLOY STEELS, MATERIALS, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, NICKEL ALLOYS, RADIATION EFFECTS, STAINLESS STEELS, STEEL-CR17NI12MO3, STEEL-CR17NI12MO3-L, STEEL-CR19NI10, STEELS, TRANSITION ELEMENT ALLOYS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Elektrokemiska metoder foer kontinuerlig maetning av korrosionshastigheter, speciellt hos hoegtemperaturutrustning av kolstaal, rostfritt 18/8 staal och zirkaloy-2
Primary Subject
Source
Oct 1971; 69 p; AE-MK--271
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Report
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INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
American Nuclear Society international meeting; Washington, D. C; 12 Nov 1972; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Trans. Amer. Nucl. Soc; v. 15(2); p. 775-776
Country of publication
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INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
Jun 1972; 126 p
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Report
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