Download or read book Corrosion of Zircaloy 4 Tubing in 68OF Water LWBR Development Program written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Seamless Zircaloy-4 tubing is utilized as fuel rod cladding in light water reactors. Water corrosion tests at 68OF have been performed to determine the corrosion and hydriding characteristics of Zircaloy-4 tubing, fabricated by cold reduction and finished in two metallurgical conditions: a stress-relief anneal (SRA) and a recrystallization anneal (RXA). These corrosion tests revealed differences in the post-transition corrosion product weight gains of the two materials. A computer corrosion model, designated CHORT, was developed from the test data and ascribes the observed difference in material weight gain to an assumed difference in the periodicity of a postulated cyclic buckling of the oxide.
Download or read book CORROSION OF ZIRCALOY 4 TUBING IN 680F WATER LWBR DEVELOPMENT PROGRAM written by G. P. Marino and published by . This book was released on with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1979 with total page 1180 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book INIS Atomindex written by and published by . This book was released on 1979 with total page 564 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Susceptibility of Unirradiated Recrystallized Zircaloy 4 Tubing to Stress Corrosion Cracking LWBR Development Program written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Stress corrosion cracking (SCC) in unirradiated recrystallized Zircaloy-4 internally pressurized tubing specimens in atmospheres containing iodine vapor, cesium, or combinations of iodine and cesium is evaluated experimentally in terms of the effects of internal surface flaw morphology, iodine and cesium concentrations, tubing hydrogen content, test temperature, and test atmosphere water vapor content on the time to failure. The iodine vapor SCC data are analyzed in the framework of a fracture mechanics model. Expressions are developed which relate the iodine SCC threshold stress and lifetime for stresses above threshold to temperature, iodine concentration, and surface flaw geometry.
Download or read book Government Reports Announcements Index written by and published by . This book was released on 1979 with total page 1108 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Government Reports Annual Index written by and published by . This book was released on 1979 with total page 954 pages. Available in PDF, EPUB and Kindle. Book excerpt: Sections 1-2. Keyword Index.--Section 3. Personal author index.--Section 4. Corporate author index.-- Section 5. Contract/grant number index, NTIS order/report number index 1-E.--Section 6. NTIS order/report number index F-Z.
Download or read book Enhancement of Aqueous Corrosion of Zircaloy 4 Due to Hydride Precipitation at the Metal Oxide Interface written by AM. Garde and published by . This book was released on 1991 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt: Long-term static autoclave corrosion tests were conducted on Zircaloy-4 tube specimens in water at 633 K. The material variables included in this investigation were: annealing parameter range 10-17 to 10-19 h (with Q/R = 40 000 K). fabrication history variation of early and late beta-quenching steps, and final heat treatment variation from several levels of stress-relief-anneal to a recrystallization anneal. Specimens were weighed at intervals of approximately 28 days for a maximum corrosion test exposure of 1160 days. The weight gain data show transitions to an accelerated corrosion rate that became apparent at exposure times greater than 300 days. The transition times varied from 141 to 253 days. Metallographic and scanning electron microscopic examination showed that the metal-oxide interface had an irregular shape and the oxidation front appeared to progress into the metal by fracture of the hydride precipitates at the interface. Hydrogen absorption fractions were calculated for each specimen and were used to estimate the hydrogen level in each specimen at the transition point. The estimated hydrogen levels at transition agreed reasonably with the hydrogen solubility in Zircaloy at 633 K. The results indicate that the corrosion rate acceleration observed in autoclaves at long times is associated with the onset of hydride precipitation and subsequent hydride fracture at the metal-oxide interface. A review of in-reactor corrosion data from the literature reveals that a similar hydride associated corrosion rate acceleration occurs in low oxygen coolant conditions in PWRs and PHWRs. Hydride precipitation at the metal-oxide interface is the probable reason for the correlation between the time of long-term autoclave corrosion rate transition and the in-PWR cladding corrosion resistance. On the basis of the effect of hydrides on the in-reactor corrosion rate, it is suggested that a better ex-reactor corrosion test to simulate the in-PWR corrosion performance would be a water test at 633 K with an imposed heat flux. The effect of hydrides on the corrosion rate is strongly related to the size, distribution, and orientation of the hydrides in the Zircaloy cross section. An alloy development program is suggested to enhance the corrosion resistance of zirconium alloys in PWRs to extended burnups.
Download or read book Recovery and recrystallization kinetics of cold worked zircaloy 4 plate and tubing LWBR LSBR Development Program written by O. M. Katz and published by . This book was released on 1968 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Corrosion of Zircaloy 4 Fuel Cladding in Pressurized Water Reactors written by LFP Van Swam and published by . This book was released on 1991 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of thermo-mechanical processing of cladding on the corrosion of Zircaloy-4 in commercial PWRs have been investigated. Visual observations and nondestructive measurements at poolside, augmented by observations in the hot cell, indicate that the initial black oxide transforms into a grey or tan and later white oxide layer at a thickness of 10 to 15 ?m independent of the thermal processing history of the tubing. At an oxide layer thickness of 60 to 80 ?m, the oxide may spall depending somewhat on the particular oxide morphology formed and possibly on the frequency of power and temperature changes of the fuel rods. Because spalling of oxide lowers the metal-to-oxide interface temperature of fuel rods, it reduces the corrosion rate and is beneficial from that point of view.
Download or read book Low Strain Diameter Expansion of Internally Pressurized Zircaloy 4 Tubing at High Temperatures LWBR Development Program written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Tests of closed-end, internally pressurized, Zircaloy-4 tubing specimens were utilized to develop low strain creep characteristics as a function of time at temperatures in the range of 1475°F to 2000°F (802°C to 1093°C) and hoop stresses in the range of 250 to 2500 psi for use in loss-of-coolant accident (LOCA) analyses. The strain rate above the start of the alpha to beta phase transformation region, approximately 1490°F (810°C), was found to be sensitive to the test procedure (stress-temperature history). This is believed to result from variations in the metallurgical structure. A prediction model is presented which provides a conservative upper bound to the low strain test data provided in this report and reported in the literature.
Download or read book Progress Relating to Civilian Applications During written by and published by . This book was released on 1962 with total page 102 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book DOE ET written by and published by . This book was released on 1980 with total page 312 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Costs of Nuclear Power written by and published by . This book was released on 1961 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Non nuclear Futures written by Amory B. Lovins and published by . This book was released on 1975 with total page 223 pages. Available in PDF, EPUB and Kindle. Book excerpt:
