Download or read book Influence of Neutron Irradiation at 55 C on the Properties of Austenitic Stainless Steels written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Types 316 and 316 + 0.23 wt % Ti stainless steels and 16-8-2 weldment were irradiated in HFIR at 55°C to fluences up to 1.35 x 1026 neutrons/m2 (

Download or read book The Combined Effects of Temperature and Irradiation on the Mechanical Properties of Austenitic Stainless Steels written by J. E. Irvin and published by . This book was released on 1965 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Neutron Irradiations at Temperatures Below 500 C on the Properties of Cold Worked 316 Stainless Steels written by JC. Van Duysen and published by . This book was released on 1994 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt: Many components used in the pressure vessel of French pressurized water reactors are made of austenitic stainless steels : 316L for screws, 304L for core barrel and baffle assembly, etc. Among these components, the most irradiated ones undergo an average damage rate of about 1 dpa/an at temperatures which may reach about 400°C. Such irradiations may have very detrimental effects on the in-service behaviour of austenitic steels. In order to forecast these effects, Electricité de France has defined important programmes of studies. In the framework of these programmes, we have carried out a review concerning the effects of irradiations at relatively low temperatures (i. e. 500°C) on cold-worked 316 stainless steel. We were particularly interested in the evolution of microstructure as well as tensile (with or without notch), creep, fatigue (with or without creep) and fracture toughness properties. In some cases, we have also analysed the influence of cold-work level, irradiation temperature and test temperature. For some mechanical properties, the data was sufficient to qualitatively predict the properties of cold worked 316 stainless steels after long -- term irradiations under PWR conditions.

Download or read book Energy Research Abstracts written by and published by . This book was released on 1993 with total page 420 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Effect of Nuclear Radiation on Structural Metals written by Frederic R. Shober and published by . This book was released on 1961 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effect of fast-neutron (>1 Mev) irradiation on the mechanical properties of structural metals and alloys was studied. Although the yield strengths and ultimate tensile strengths are increased su stantially for most materials, the ductility suffers severe decreases. This report presents these changes in properties of several structural metals for a number of neutron exposures within the 1.0 x 10 to the 18th power to 5.0 x 10 to the 21st power n/sq cm range. Data summarizing these effects on several classes of materials such as carbon steels, low-alloy steels, stainless steels, Zr-base alloys, ni-base alloys, Al-base alloys, and Ta are given. Additional data which show the influence f irradiation temperatures and of post-irradiation annealing on the radiation-induced property changes are also given and discussed. Increases as great as 175% in yield strength, 100% in ultimate strength, and decreases of 80% in total elongation are reported for fast-neutron exposures as great as 5 10 to the 21st power n/sq cm. (Author).

Download or read book The Effects of Neutron Irradiation on Fracture Toughness of Austenitic Stainless Steels written by and published by . This book was released on 1999 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: Austenitic stainless steels are used extensively as structural alloys in reactor pressure vessel internal components because of their superior fracture toughness properties. However, exposure to high levels of neutron irradiation for extended periods leads to significant reduction in the fracture resistance of these steels. This paper presents results of fracture toughness J-R curve tests on four heats of Type 304 stainless steel that were irradiated to fluence levels of (almost equal to)0.3 and 0.9 x 1021 n cm−2 (E>1 MeV) at (almost equal to)288 C in a helium environment in the Halden heavy water boiling reactor. The tests were performed on 1/4-T compact tension specimens in air at 288 C; crack extensions were determined by both DC potential and elastic unloading compliance techniques.

Download or read book Effects of Residual Elements on Properties of Austenitic Stainless Steels written by and published by . This book was released on 1967 with total page 152 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1994 with total page 1038 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Radiation Effects on the Mechanical Properties and Microstructure of Type 304 Stainless Steel written by J. S. Armijo and published by . This book was released on 1964 with total page 94 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Irradiation on the Mechanical Properties of Austenitic Stainless Steels Under Dynamic Loading written by C. Albertini and published by . This book was released on 1979 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: Effects of strain rate and temperature on AISI 316L austenitic stainless steel irradiated to a dose of 2.2 displacements per atom (dpa) have been examined. Strain rates ranged between 10-2 s-1 and 102 s-1. Temperatures were ambient and 400°C. Techniques used for preparation of specimens and testing are described together with experimental results. The superposition of the effects of strain rate and irradiation causes important reduction of ductility both at room and at high temperature. Therefore, special cautions should be taken in fixing safety coefficients for the calculation of dynamically loaded structures, such as pressure vessels, in case of an accident in fast breeder reactors.

Download or read book Properties of Austenitic Stainless Steels and Their Weld Metals Influence of Slight Chemistry Variations written by C. R. Brinkman and published by ASTM International. This book was released on 1979 with total page 155 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys written by John Moteff and published by ASTM International. This book was released on 1973 with total page 560 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effect of Neutron Irradiation on Mechanical Properties of AISI Type 347 Stainless Steel written by M. Kangilaski and published by . This book was released on 1967 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: Changes in mechanical properties induced by irradiation of AISI Type 347 stainless steel at about 60 C were determined after integrated fast-flux (>1 Mev) exposures of 1.6 x 1022 and 2.1 x 1022 n/cm2. Tension tests were performed at room temperature, 316, and 750 C. The results indicated that the ultimate tensile strength and yield strength were greater after irradiation, with the yield strength showing the greater increase. After an exposure of 2.1 x 1022 n/cm2, the ratio of yield strength to ultimate strength was approximately 1. The decreases in ductility as measured by total and uniform elongation at 20 C were about the same magnitude for both levels of irradiation. The ductility at 316 C continued to decrease as a function of increasing neutron exposure. Radiation-induced property changes differed only slightly from those observed after irradiation to 5.5 x 1021 n/cm2 with the exception of the uniform and the total elongation at 316 C, suggesting that saturation of displacement damage occurred prior to this exposure. The fracture mode for both unirradiated and irradiated specimens was transgranular. Annealing of irradiated specimens for 1 hr at 982 C restored the preirradiation mechanical properties at 316 C. A severe reduction in ductility was noted for specimens tested at 750 C after irradiation to 2.1 x 1022 n/cm2, showing only about 0.5 per cent as uniform and total elongation. The fracture mode was intergranular. Annealing for 1 hr at 982 and 1350 C did not change the as-irradiated ductility.

Download or read book Reactor Materials written by and published by . This book was released on 1970 with total page 192 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 1070 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Advances in the Technology of Stainless Steels and Related Alloys written by and published by ASTM International. This book was released on 1983 with total page 364 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effect of Irradiation on the Mechanical Properties of 19 9DL Alloy written by CJ. Baroch and published by . This book was released on 1970 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: Austenitic stainless steels, which are used extensively in water cooled nuclear reactors, are presently being considered for use in fast reactors; however, these steels are susceptible to irradiation embrittlement and irradiation induced swelling. The modified austenitic stainless steel 19-9DL alloy, on the other hand, exhibits good creep strength at high temperatures. Babcock & Wilcox conducted an exploratory program to determine the effects of irradiation on 19-9DL alloy at temperatures of 55 C (130 F), 343 C (650 F), and 413 C (775 F). The maximum fluence in this program (9.2x1020 n/cm2, E>1 MeV) was too low to prove the suitability of the alloy's potential for fast reactor applications but did show that additional evaluation of the alloy for fast reactors was warranted. The results indicate that the alloy is suitable for use in thermal reactors, since the ductility at 413 C was greater than 10 percent at a fluence approaching 1x1021 n/cm2, E>1 MeV.