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Cherry, J.L.
Sandia National Labs., Albuquerque, NM (United States). Funding organisation: Nuclear Regulatory Commission, Washington, DC (United States)1996
Sandia National Labs., Albuquerque, NM (United States). Funding organisation: Nuclear Regulatory Commission, Washington, DC (United States)1996
AbstractAbstract
[en] Corrosion damage to a nuclear power plant containment structure can degrade the pressure capacity of the vessel. For the low-carbon, low- strength steels used in containments, the effect of corrosion on material properties is discussed. Strain-to-failure tests, in uniaxial tension, have been performed on corroded material samples. Results were used to select strain-based failure criteria for corroded steel. Using the ABAQUS finite element analysis code, the capacity of a typical PWR Ice Condenser containment with corrosion damage has been studied. Multiple analyses were performed with the locations of the corrosion the containment, and the amount of corrosion varied in each analysis
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1996; 11 p; 1996 international mechanical engineering congress and exhibition; Atlanta, GA (United States); 17-22 Nov 1996; CONF-961105--17; CONTRACT AC04-94AL85000; Also available from OSTI as DE96014031; NTIS; US Govt. Printing Office Dep
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AbstractAbstract
[en] The influence of normalizing time and temperature, as well as the plate thickness, on the impact properties of ASTM A-516 grade 70 steel, is studied. Results show that different normalizing conditions may lead to equivalent microstructure with different impact properties. Normalizing conditions that cause low cooling rate in the critical zone exhibit banded microstructure with inferior impact properties. (Author)
[pt]
Estuda-se a influencia da temperatura e tempo de normalizacao, alem da espessura da chapa a ser normalizada, nas propriedades de impacto do aco ASTM A-516 grau 70. Verificou-se que diferentes condicoes de normalizacao podem proporcionar microestruturas equivalentes, porem com diferentes propriedades de impacto. Determinadas condicoes de normalizacao, que conduzam a baixas velocidades de resfriamento na zona critica, fornecem estruturas bandeadas, com propriedades de impacto inferiores aquelas desejadas. (Autor)Original Title
Efeitos das variaveis de normalizacao nas propriedades de impacto do aco ASTM A-516 grau 70
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1982; 20 p; 37. Annual Congress of the Brazilian Association of Metals; Rio de Janeiro (Brazil); Jul 1982
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Carranza, R.M; Esquivel, C.M; Giordano, C.M
CONAMET/SAM 'Simposio materia 2002'. Proceedings of the congress2002
CONAMET/SAM 'Simposio materia 2002'. Proceedings of the congress2002
AbstractAbstract
[en] The kinetics of the corrosion of A516 steel used as a material for storage tanks for highly active liquid nuclear wastes is studied here. Despite the complexity of the composition of the simulated wastes used, the technique of electrochemical impedance could be used to quantify the corrosion speed based on the high frequency resistance obtained from the test results of the parameters of an equivalent 2RC cascade circuit. The low frequency parameters are associated with the redox processes of the passive film. An approximate method is proposed to evaluate the corrosion speed in these systems with just a potential lineal sweeper since in these cases the slope of the potential/current curve cannot be assimilated to the load transfer resistance (CW)
Original Title
Influencia de la composicion de residuos nucleares liquidos en la corrosion de los tanques de almacenamiento
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Universidad de Chile, Facultad de Ciencias Fisicas y Matematicas, Santiago (Chile); 995 p; Nov 2002; p. 447-452; CONAMET/SAM 'Simposio materia 2002'; CONAMET/SAM Simposio materia 2002; Santiago, Chile (Chile); 12-15 Nov 2002; Available from Library of CCHEN
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AbstractAbstract
[en] Surface cracks in ASTM A516 Gr 70 were grown in fatigue under pure bending loads. Experiment results were compared to predictions made following, the guidelines of the ASME Boiler and Pressure Vessel Code, Section XI. An attempt was made to improve the predictions by including the effect of crack shape change (as observed in the experiments) and by varying the material parameters input to the analysis. It was found that good predictions could be made following the Section XI guidelines, although growth rates at a given stress intensity amplitude appeared to be somewhat lower than expected from results using compact tension specimens for the same material under similar conditions. (orig.)
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Commission of the European Communities, Brussels (Belgium); Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris; vp; ISBN 0 444 86265 X; ; 1981; p. L8/4; North-Holland Publishing Co; Amsterdam (Netherlands); 6. international conference on structural mechanics in reactor technology; Paris (France); 17 - 21 Aug 1981
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Sunaryo, Geni Rina; Sumijanto; Nurul L, Siti
Proceeding of the Fifth Scientific Presentation on Nuclear Safety Technology2000
Proceeding of the Fifth Scientific Presentation on Nuclear Safety Technology2000
AbstractAbstract
[en] The final objective of this research is to design the mini scale of desalination installation. It has been started from 1997/1998 and has been doing for this 3 years. Where the study on the assessment of various desalination system has been done in the first year and thermodynamic in the second year. In this third year, literatully study on material resistance from outside pressure has been done. The number of pressure for single evaporator flashing method is mainly depend on the temperature that applied in that system. In this paper, the configuration stage, the choice method of selecting material for main evaporator vessel, tube, tube plates, water boxes, pipework, and valves for multistage flash distillation will be described. The choice of selecting material for MSF is base on economical consideration, cheap, high resistance and easy to be maintained
Original Title
Aspek-Aspek Pemilihan Material Yang Mempengaruhi Evaporasi Tunggal Metoda Flashing
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Suhaemi, Tj.; Sudarno; Sunaryo, G. R.; Supriatna, P.; Antariksawan, A. R.; Sumijanto; Febrianto; Histori; Aliq (National Nuclear Energy Agency, Serpong (Indonesia)) (eds.); Center for Development of Nuclear Safety Technology, National Nuclear Energy Agency, Serpong (Indonesia); 314 p; ISSN 1410-0533; ; 28 Jun 2000; p. 93-99; 5. Scientific Presentation on Nuclear Safety Technology; Presentasi Ilmiah Teknologi Keselamatan Nuklir V; Serpong (Indonesia); 28 Jun 2000; Also available from Center for Development of Informatics and Computation Technology, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 3 figs; 6 refs
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Vassilaros, M.G.; Gudas, J.P.; Joyce, J.A.
Naval Ship Research and Development Center, Annapolis, MD (USA)1982
Naval Ship Research and Development Center, Annapolis, MD (USA)1982
AbstractAbstract
[en] The objective of this investigation was to extend the range of tearing-instability validation experiments utilizing the compact specimen to include high-toughness alloys. J-Integral tests of ASTM A106; ASTM A516, Grade 70; ASTM A533B; HY-80; and HY-130 steels were performed in a variably compliant screw-driven test machine. Results were analyzed with respect to the materials JI-R curves and various models of Tapplied for the compact specimen. Tearing instability theory was validated for these high-toughess materials. For the cases of highly curved JI-R curves, it was shown that the actual value of Tmaterial at the point of instability should be employed rather than the average Tmaterial value. The Tapplied analysis of Paris and coworkers applied to the compact specimen appears to be nonconservative in predicting the point of instability; whereas, the Tapplied analysis of Ernst and coworkers appears to be accurate, but requires precision beyond that displayed in this program. The generalized Paris analysis applied to the compact specimen and evaluated at maximum load was most consistent in predicting instability. 16 figures, 3 tables
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ASTM/A106; HY80; HY130
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Aug 1982; 45 p; Available from NTIS, PC A03/MF A01 - GPO as DE83900676
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Witt, F.J.
Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Energy Systems Div1980
Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Energy Systems Div1980
AbstractAbstract
[en] A low Charpy shelf steel is defined in this report as a steel which has a Charpy impact energy sufficiently low (less than 50 ft-lbs) to mitigate the determination of RT/sub NDT/ as defined by Appendix G of Section III of the ASME code. Six steels (one in both the irradiated and the unirradiated states) with Charpy shelf energies between 30 and 60 ft-lbs are evaluated. The evluation is based on an examination of the Charpy impact curves and fracture toughness parameters such as K/sub Ic/ and K/sub Ia/. One material was a low Charpy shelf steel for which both unirradiated and irradiated results are considered. Two of the materials are degraded (quenched only) carbon steels while a third is a high strength rotor forging steel. One material is a pipe steel and one is an ordinary carbon structural steel
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Apr 1980; 46 p; Available from NTIS., PC A03/MF A01 as DE82010860
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Bernard-Connolly, M.; Biron, A.; Bui-Quoc, T.
Fourth international conference on pressure vessel technology. Volume 11980
Fourth international conference on pressure vessel technology. Volume 11980
AbstractAbstract
[en] Many components in Candu-type nuclear power plants such as heat exchangers and pressurizers are fabricated from normalized SA-516 grade 70 steel. Such components are usually operated with variable loadings at high temperature and little information concerning the fatigue properties of this material is presently available. The purpose of the present investigation is to provide some elements of that information. Tests have been carried out at 20 and 4270C with controlled cyclic strain at a fixed temperature, first at constant amplitude to establish standard fatigue curve, and then with two increasing or decreasing strain levels for cumulative damage study. In addition, two constant amplitude fatigue tests were carried out at 5380C. The present work is a continuation of experimental studies on the low cycle fatigue behaviour of materials. In particular, test results on 304 stainless steel at 20, 538 and 6500C with two strain levels have shown that the order of strain applications and the differences between the strains involved are important parameters in the summation of cycle ratios. In this paper, test results on SA-516-70 are reported. The fatigue curve and remaining life are discussed with an emphasis on evaluation methods which have been developed from a cumulative damage concept applicable to fatigue studies with controlled strain. (author)
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Institution of Mechanical Engineers, London (UK); 409 p; ISBN 0 85298 459 6; ; 1980; p. 297-301; Mechanical Engineering Pubs. Ltd., for the Institution of Mechanical Engineers; London; 4. international conference on pressure vessel technology; London, UK; 19 - 23 May 1980
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AbstractAbstract
[en] Full-text: The used of ultrasonic testing as a thickness measurement for structural components (pipeline and pressure vessel) is among the popular inspection tool widely use in the industrial power plant such as at petrochemical and nuclear power plant. Currently, there are cases where the thickness grows and the result will affect the reliability of the test. There are many factors that can affect the reliability of measurement. One of it is the material under test itself. In the Malaysian Nuclear Agency, initial efforts are underway to study the understanding on the effects of heat treatment to the sound velocity and microstructure changes of ASTM A516 steel. Few samples of thin square shaped prepared were heat treated under the following conditions: austenitization at 9800 degree Celsius - 2 hours, quenching; tempering at various temperature 4000, 5000, 6000 and 7000 degree Celsius. The results show that the microstructure changes and samples exhibit different sound velocity at different heat treatment. (author)
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2010; 1 p; RnD Seminar 2010: Research and Development Seminar 2010; Bangi (Malaysia); 12-15 Oct 2010; Available in abstract form only, full text entered in this record; Poster presentation
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AbstractAbstract
[en] A study has been made of electron beam (EB) welding procedures for heavy section steel plates. The materials are carbon steel (ASTM A516 Gr. 70) and 2.25Cr-1Mo steel (ASTM A387 Gr. 22 C12) with thickness in the range 50 to 200 mm. Porosity and solidification crack were identified as the two major defects. They depended strongly on the solidification pattern for such steels with low oxygen and nitrogen content and could be prevented by the selection of welding procedures. Beam oscillation was the effective technique to prevent weld defects. Horizontal position was found to be preferred for welding steel plates more than 100 mm thick and sound welds could be obtained in 200 mm thick steel plates. The Charpy impact properties have been examined. Very good results were obtained in 2.25Cr-1Mo steel for weld metal and HAZ. As for carbon steels, reduction in Ceq. of base metal was beneficial to improve toughness. The toughness of A516-Gr. 70 steel containing 0.21% C was very poor in the as-welded condition, while good toughness could be obtained after PWHT. HAZ Charpy properties were generally superior to those of weld metal. Results of other joint properties such as tension, bend, hardness, COD, creep rupture and NRL drop weight tests were also satisfactory
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David, S.A.; Slaughter, G.M. (comps.); Oak Ridge National Lab., TN (USA); p. 331-343; Sep 1982; p. 331-343; International conference on welding technology for energy applications; Gatlinburg, TN (USA); 16 - 19 May 1982; Available from NTIS, PC A99/MF A01; 1 as DE83006404
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