Download or read book Effect of Hydrogen and Neutron Irradiation on the Failure of Flawed Zircaloy 2 Pressure Tubes written by A. Cowan and published by . This book was released on 1968 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Effect of Hydrogen and Neutron Irradiation on the Failure of Flawed Zircloy 2 Pressure Tubes written by Atomic Energy of Canada Limited and published by . This book was released on 1969 with total page 35 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 1974 with total page 786 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation Effects on Structural Alloys for Nuclear Reactor Applications written by A. L. Bement and published by ASTM International. This book was released on 1971 with total page 571 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Materials written by and published by . This book was released on 1969 with total page 536 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Core Materials written by and published by . This book was released on 1968 with total page 612 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Crack Propagation Tests on Zircaloy 2 Reactor Pressure Tubing in Both the Normal and Hydrided Conditions written by R. C. Aungst and published by . This book was released on 1965 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Whether a reactor pressure tube failure is ductile or brittle could spell the difference between an annoying incident and one producing ruinous mechanical damage to the plant. For this reason, it was imperative that a test be provided to assess directly the resistance to brittle failure of Zircaloy-2 pressure tubes. Theories of brittle fracture as applied to tubular configurations do not appear to be advanced enough to allow confident prediction of behavior based on indirect tests such as Charpy impact, drop weight, and others. Two methods were developed for introducing a starting crack in specimens of pressure tubing under controlled conditions of temperature and stress. Using these methods, data have been generated defining the effects of temperature, degree of cold-work, flaw size, hydrogen content, and a moderate amount of irradiation on susceptibility to brittle fracture. The tests indicate that at elevated temperatures likely to be encountered in reactor operation there exists no tendency toward brittle fracture arising from defects of the order of 1/2 in. long. At 150 C and below susceptibility to brittle failure increases with degree of cold-work. Since irradiation and cold-work have similar effects on strength and ductility it seems reasonable to expect brittle fracture to occur more readily with increasing exposure to reactor environment. Hydrogen content lowers the resistance to brittle failure at room temperature of a tube containing a flaw and increases the sensitivity of the test to flaw size. Continuing tests will explore the effects of increased flaw size and hydrogen content, elevated temperatures, and the effects of further irradiation.
Download or read book Reactor Technology written by and published by . This book was released on 1970 with total page 448 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Implications of Embrittlement During the Life of a Zirconium Pressure Tube Reactor written by R.W. Nichols and published by . This book was released on 1966 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Monthly Accession List written by Radiation Effects Information Center (Columbus, Ohio). and published by . This book was released on 1969-07 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Embrittlement of Zircaloy 2 Pressure Tubes written by B. Watkins and published by . This book was released on 1968 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Power Reactor Technology and Reactor Fuel Processing written by and published by . This book was released on 1967 with total page 1110 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Peaceful Uses of Atomic Energy Effects of irradiation on fuels and materials written by and published by . This book was released on 1972 with total page 640 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Crack Propagation Tests on Normal and Hydrided Zircaloy 2 Reactor Pressure Tubing written by R. C. Aungst and published by . This book was released on 1964 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Power Reactor Instrumentation Systems Handbook written by Joseph M. Harrer and published by . This book was released on 1973 with total page 1052 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Neutron Irradiation and Cold Work Effects on Zircaloy 2 Corrosion and Hydrogen Pickup written by H. P. Maffei and published by . This book was released on 1964 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nearly 200 pre-autoclaved and weighed coupons of reactor-grade Zircaloy-2 in the annealed, 10, 20, and 40 per cent cold-worked condition have been exposed to the fast neutron flux of the Engineering Test Reactor (ETR) in nominal 540 F pH 10 water for up to 125 days. Flux intensity varied from 0.17 to 1.04 x 1014 nv (>1 Mev), and integrated neutron exposures ranged from 0.3 to 8.2 x 1020 nvt. Comparisons of weight gain and hydrogen pickup results among irradiated specimens and with unirradiated control coupons were used to broaden the area of present knowledge relative to the combined effects of neutron irradiation and cold work on surface chemical reactions and hydrogen absorption in Zircaloy-2. In general, exposure to the in-core coolant environment of the ETR causes an order-of-magnitude increase in average corrosion rates, similar to the effect of superheated steam at a temperature approximately 200 F above the irradiation temperature. In-reactor weight-gain data exhibit an apparent saturation effect with increasing flux intensity, and measured weight gains have been confirmed by optical measurements of oxide film thickness. Direct visual observations and photography at magnifications up to 40 x of irradiated coupons oxidized to weight gains as high as 150 mg/dm2 showed the surfaces to be smooth, glossy, and dark gray or blue-black in color. Some of the coupons appeared to be streak stained, but there were no indications of blistering, spalling, or light-colored oxide even at sharp edges and corners. No significant or consistent variation of weight gain with cold work has been found for material exposed in- or out-of-reactor. No significant effect of flux intensity or integrated flux on hydrogen sorption was observed.
Download or read book Metals Abstracts written by and published by . This book was released on 1994 with total page 1586 pages. Available in PDF, EPUB and Kindle. Book excerpt:
