Download or read book Neutron Irradiation Creep at 100 C on 316L AMCR and Welded 316L Stainless Steel Alloys written by H. Hausen and published by . This book was released on 1999 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: We performed measurements on the elongation of many different austentic stainless steel alloys irradiating at 100°C in a low flux channel of the High Flux Reactor at Petten varying the applied stress between zero and 300 MPa. We irradiated in total 98 samples in two irradiation rigs. Of these samples only 26 samples could be tested up to a dose of 2.1 dpa, and 13 samples up to a dose of 0.21 dpa. The steels tested are listed in Table I. In the second irradiation rig four TIG-welded samples and one EB-welded sample were irradiated.
Download or read book Effects of Radiation on Materials written by R. K. Nanstad and published by ASTM International. This book was released on 1999 with total page 1135 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation Creep at Temperatures of 400 C and Below for Application to Near Term Fusion Devices written by ML. Grossbeck and published by . This book was released on 1999 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of six austenitic stainless steels and two ferritic alloys were irradiated sequentially in two research reactors where the neutron spectrum was tailored to produce a He transmutation rate typical of a fusion device. Irradiation began in the Oak Ridge Research Reactor. After an atomic displacement level of 7.4 dpa was achieved, the specimens were moved to the High Flux Isotope Reactor for the remainder of the 19 dpa accumulated. Irradiation temperatures of 60, 200, 330, and 400°C were studied with internally pressurized tubes of type 316 stainless steel, PCA, HT 9, and a series of four laboratory heats of: Fe-13.5Cr-15Ni, Fe-13.5Cr-35Ni, Fe-13.5Cr-15Ni- 0.18Ti, and Fe-16Cr. At 330°C, irradiation creep was shown to be linear with fluence and stress. There was little or no effect of cold-work on creep under these conditions at all temperatures investigated. The HT9 demonstrated a large deviation from linearity at high stress levels, and a minimum in irradiation creep with increasing stress was observed in the Fe-Cr-Ni ternary alloys.
Download or read book Properties of Reactor Structural Alloys After Neutron Or Particle Irradiation written by C. J. Baroch and published by ASTM International. This book was released on 1975 with total page 640 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Mechanical Behaviour and Nuclear Applications of Stainless Steel at Elevated Temperatures written by Metals Society and published by Ashgate Publishing. This book was released on 1982 with total page 276 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation Creep in Austenitic Stainless Steels at 60 to 400 C with a Fusion Reactor Helium to Dpa Ratio written by M. P. Tanaka and published by . This book was released on 1990 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation creep was investigated in the alloys--prime candidate alloy (PCA), Japanese Fusion Energy Program (JPCA), and American Iron and Steel Institute (AISI) 316 (UNS S31600) stainless steel. Tubes pressurized to stress levels of 50 to 400 MPa were irradiated in the Oak Ridge Research Reactor (ORR) with the neutron spectrum tailored to achieve the fusion reactor helium:dpa value of 12 appm/dpa in AISI 316 stainless steel. Irradiation temperatures of 60, 330, and 400°C were investigated, and the irradiation produced 8 dpa and a maximum of about 100 appm helium. Irradiation creep rates of 2.2 to 14x10-4MPa-1dpa-1 were observed at 60°C. At 330 and 400°C irradiation creep rates of 1.3 to 3.5x10-4 were observed, similar to those found previously in similar experiments in the ORR. The low temperature irradiation creep was interpreted in terms of a new model for irradiation creep based on transient climb-enabled glide. The results are important in the design of experimental fusion reactors where temperatures below 100°C are being considered for the operation of high flux components.
Download or read book Effects of Neutron Irradiation on Creep Rupture Properties of Type 316 Stainless Steel Tubes written by I. P. Bell and published by . This book was released on 1969 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of irradiation in the Dounreay Fast Reactor and the Dounreay Materials Testing Reactor on the creep-rupture-properties of Type 316 stainless steel tubing were investigated. DFR irradiation produced a loss of rupture ductility but, in general, no change in creep strength in 650 C biaxial tests of solution-treated material. Cold-worked tubes suffered a loss of 550 C creep strength. Irradiation of solution-treated tubes at 650 C in DMTR caused a severe loss of high-temperature ductility and a tenfold reduction of creep rate both during and after irradiation. It is possible that an irradiation-induced carbide precipitation process is responsible for the increase of creep strength.
Download or read book Chemical Abstracts written by and published by . This book was released on 2002 with total page 2566 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Determination of Creep Compliance and Creep swelling Coupling Coefficients for Neutron irradiated Titanium modified Stainless Steel at 00 C written by and published by . This book was released on 1991 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation creep data from FFTF-MOTA at ∼400°C were analyzed for nine 20% cold-worked titanium-modified type 316 stainless steels, each of which exhibits a different duration for the transient regime of swelling. One of these steels was the fusion prime candidate alloy designated PCA. The others were various developmental breeder reactor heats. The analysis was based on the assumption that the B0 + DS creep model applies to these steels at this temperature. This assumption was found to be valid. A creep-swelling coupling coefficient of D ≈ 0.6 × 10−2 MPa−1 was found for all steels that had developed a significant level of swelling. This result is in excellent agreement with the results of earlier studies conducted in EBR-II using annealed AISI 304L and also 10% and 20% cold-worked AISI 316 stainless steels. There appears to be some enhancement of swelling by stress, contradicting an important assumption in the analysis and leading to an apparent but misleading nonlinearity of creep with respect to stress.
Download or read book Irradiation Creep and Stress Affected Swelling in Austenitic Stainless Steel 16Cr 15Ni 3Mo Nb B Irradiated in the BN 350 Reactor written by AN. Vorobjev and published by . This book was released on 2000 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation creep and void swelling are important damage processes for stainless steels when subjected to neutron irradiation at elevated temperatures. To date, most published data of this type have been derived from steels prepared by various Western nations and Japan. This paper describes the results of an experiment involving irradiation of gas-pressurized tubes constructed from Russian niobium-stabilized austenitic steel EP-172 of type 16Cr-15Ni-3Mo-Nb doped with boron. The tubes were irradiated in the lowenrichment zone of the BN-350 fast reactor to three doses of 20, 45 and 60 dpa at temperatures in the range of 480-520°C.
Download or read book Data Collection on the Effect of Irradiation on the Mechanical Properties of Austenitic Stainless Steels and Weld Metals written by A-A Tavassoli and published by . This book was released on 1996 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.:• increases in tensile proof strength,• reductions in tensile ductility,• decreases in impact energy,• reductions in creep-rupture strength and ductility, and • reductions in creep-fatigue endurance.
Download or read book Alloys Index written by and published by . This book was released on 1988 with total page 1058 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Atlas of Stress strain Curves written by ASM International and published by ASM International. This book was released on 2002-01-01 with total page 821 pages. Available in PDF, EPUB and Kindle. Book excerpt: Contains more than 1400 curves, almost three times as many as in the 1987 edition. The curves are normalized in appearance to aid making comparisons among materials. All diagrams include metric units, and many also include U.S. customary units
Download or read book Electrostatic Levitator written by and published by . This book was released on 1999 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Phase Stability During Irradiation written by Metallurgical Society of AIME Staff and published by . This book was released on with total page 629 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Joining of Ceramics written by M.G. Nicholas and published by Springer. This book was released on 1990 with total page 240 pages. Available in PDF, EPUB and Kindle. Book excerpt: An examination of the methods used and the types of bonding that occur in the joining of ceramics to glass or metals, both on surfaces and at joints. The book deals with both the physical and chemical aspects of the bonding.
Download or read book High temperature Corrosion Studies written by A. F. Baker and published by . This book was released on 1966 with total page 492 pages. Available in PDF, EPUB and Kindle. Book excerpt:
