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 Energy Research Abstracts written by and published by . This book was released on 1978 with total page 424 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book INIS Atomindeks written by and published by . This book was released on 1978 with total page 1206 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 1978 with total page 1204 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 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 Strength and Metallurgical Properties of the Zircaloy 2 Pressure Tubes for the PRTR written by R. L. Knecht and published by . This book was released on 1962 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Simulated Fuel Expansion Testing of Zircaloy Tubing written by JP. Foster and published by . This book was released on 1989 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: Expanding mandrel (Simulated Fuel Expansion or Simfex) pellet-cladding interaction (PCI) simulation tests were performed on unirradiated Zircaloy-2, Zircaloy-4, zirconium-lined Zircaloy-2, Zircaloy-3A alloy-lined Zircaloy-2, and graphite-lined Zircaloy-4 tubing with high-purity argon and iodine. SIMFEX tests were also performed on irradiated Zircaloy-4 cladding in iodine. Sensitivity tests were performed on unirradiated unlined Zircaloy-4 tubing in order to establish SIMFEX test conditions that simulate PCI. Test variables included test temperature, core compression rate (or sample strain rate) and iodine partial pressure. SIMFEX test parameters that simulate PCI cover a wide range of test conditions. At a given temperature, these test conditions depend on core compression rate and iodine partial pressure. Iodine SIMFEX tests on unlined unirradiated and irradiated Zircaloy-4 showed that the PCI simulation test conditions produce fractures similar to fuel rod ramp tests. The zirconium-lined Zircaloy-2, Zircaloy-3A alloy-lined Zircaloy-2 and graphite-lined Zircaloy-4 tubing exhibited excellent resistance to simulated PCI failure. Similar diameter fracture strains were exhibited by the zirconium-lined Zircaloy-2 and Zircaloy-3A alloy-lined Zircaloy-2 while significantly higher diameter fracture strains were measured on the graphite-lined Zircaloy-4 tubing. The results of these tests will be used to discuss iodine stress corrosion cracking liner performance mechanisms.

Download or read book Government Reports Announcements Index written by and published by . This book was released on 1978 with total page 1584 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book High temperature Deformation and Rupture Behavior of Internally pressurized Zircaloy 4 Cladding in Vacuum and Steam Enivronments LOCA Conditions written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The high-temperature diametral expansion and rupture behavior of Zircaloy-4 fuel-cladding tubes have been investigated in vacuum and steam environments under transient-heating conditions that are of interest in hypothetical loss-of-coolant accident situations in light-water reactors. The effects of internal pressure, heating rate, axial constraint, and localized temperature nonuniformities in the cladding on the maximum circumferential strain have been determined for burst temperatures between approximately 650 and 1350°C.

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 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 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 On predicting the expansion of zircaloy tubing in variable high temperature environments written by W. R. Clendening and published by . This book was released on 1973 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report summarizes the results of a portion of a research program which is intended to provide a basis for future designs of nuclear reactor fuel capable of surviving a loss of coolant accident (loca). the work reported is an analysis of 300 experiments that were required to indicate the strength and deformation characteristics of fuel cladding during thermal transients similar to those which would occur during a loca. a mathematical model which estimates the uniform expansion associated with a tube being heated at a constant heating rate is developed. it is expected that if a few additional experiments are performed in order to more accurately define the coefficients of this model (for heating rates other than 25 degrees c/sec), then it should provide a reasonable estimate of fuel clad behaviour (for epsilon less than or equal to 10 percent) during the initial and most difficult to describe stage of a loca in which both temperature and strain rate are rapidly varying.

Download or read book Reactor Technology written by and published by . This book was released on 1971 with total page 388 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book High temperature expansion and rupture behaviour of zircaloy tubing written by D. G. Hardy and published by . This book was released on 1973 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Metallographic Standards for Estimating Hydrogen Content of Zircaloy 4 Tubing written by B. Z. Hyatt and published by . This book was released on 1982 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Characterization of Zircaloy 4 Tubing Procured for Fuel Cladding Research Programs written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A quantity of Zircaloy-4 tubing (10.92 mm outside diameter by 0.635 mm wall thickness) was purchased specifically for use in a number of related fuel cladding research programs sponsored by the Division of Reactor Safety Research, Nuclear Regulatory Commission (NRC/RSR). Identical tubing (produced simultaneously and from the same ingot) was purchased concurrently by the Electric Power Research Institute (EPRI) for use in similar research programs sponsored by that organization. In this way, source variability and prior fabrication history were eliminated as parameters, thus permitting direct comparison (as far as as-received material properties are concerned) of experimental results from the different programs. The tubing is representative of current reactor technology. Consecutive serial numbers assigned to each tube identify the sequence of the individual tubes through the final tube wall reduction operation. The report presented documents the procurement activities, provides a convenient reference source of manufacturer's data and tubing distribution to the various users, and presents some preliminary characterization data. The latter have been obtained routinely in various research programs and are not complete. Although the number of analyses, tests, and/or examinations performed to date are insufficient to draw statistically valid conclusions with regard to material characterization, the data are expected to be representative of the as-received tubing. It is anticipated that additional characterizations will be performed and reported routinely by the various research programs that use the tubing.