Download or read book Fretting Wear Behavior of Zircaloy 4 OPTINTM and ZIRLOTM Fuel Rods and Grid Supports Under Various Autoclave and Hydraulic Loop Endurance Test Conditions written by MY. Young and published by . This book was released on 2005 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt: High fuel duty, eighteen-month and longer cycle lengths, and higher burnups have put increased demands on pressurized water reactor (PWR) fuel during recent years. As a result of these demanding operating conditions, the fretting-wear performance of PWR fuel rods against structural grid supports is being challenged. To understand the in-reactor fretting-wear performance of PWR fuel, Westinghouse Electric Company (W) and Atomic Energy of Canada Limited (AECL) have performed investigations to study the fretting-wear behavior of zirconium alloy nuclear fuel rods and grid supports. Experimental work was carried out at the AECL Chalk River Laboratories (Canada) in autoclave impact fretting-wear test machines and at the W Columbia, South Carolina (USA) plant in the Westinghouse -- Vibration Investigation Pressure-Drop Experimental Research (VIPER) hydraulic test loop.

Download or read book Oxidation and the Testing of Turbine Oils written by Cyril A. Migdal and published by ASTM International. This book was released on 2008 with total page 929 pages. Available in PDF, EPUB and Kindle. Book excerpt: This work presents papers from a December 2005 symposium held in Norfolk, Virginia, and sponsored by ASTM Committee D2 on Petroleum Products and Lubricants and its Subcommittees D02.09 on Oxidation and D02.C0 on Turbine Oils. Contributors include equipment manufacturers, end users, lubricant producers, lubricant additive suppliers, test equipment manufacturers, and standard test method developers. They share information on industry trends, evolving technologies, and changing equipment designs and operating conditions, with a focus on how these factors impact oxidation. Some topics covered include turbine oil performance limits, a new form of the rotating pressure vessel oxidation test, and degradation mechanisms leading to sludge and varnish in modern turbine oil formulations. B&w photos are included. There is no subject index. Migdal is affiliated with Chemtura Corporation.

Download or read book Effects of Water Chemistry and Types of Motion on the Fretting wear Behaviour of Zirconium Alloy Components at High Temperature written by Thierry Joulin and published by . This book was released on 1999 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fretting-wear tests were conducted at high temperature and pressure to simulate the interactions occurring between the fuel claddings made of Zircaloy-4 and the supporting structure. The experiments consisted of two phases to investigate (1) the effect of water chemistry and (2) the type of fuel rod-to-spacer grid relative motion. The first phase, which consisted of six experiments, showed that boron and lithium hydroxide additions in water chemistry does not have a significant effect on fuel rod wear compared to ammonium hydroxide addition. In the second phase, a test machine was developed and commissioned to study bidirectional motions, prior to investigating the effects of types of fuel rod-to-spacer grid motion on fuel rod wear. Then eight tests were conducted. The type of motion and the level of static force applied were both found to have a strong effect on fuel rod wear coefficients.

Download or read book A Comparison of Transient Heating Burst Test Results of Unirradiated and Irradiated Zircaloy 4 Fuel Rod Cladding written by LM. Lowry and published by . This book was released on 1982 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Nuclear Regulatory Commission supported an experimental program to study the mechanical properties of both unirradiated and irradiated fuel rod cladding. The program was designed to produce a mechanical property data base for use in developing modeling codes which could then be used to predict the performance of Zircaloy-4 clad fuel rods under various reactor loss-of-coolant accident (LOCA) conditions. Transient-heating burst tests were conducted at Argonne National Laboratory, Battelle Columbus Laboratories, and Oak Ridge National Laboratory as part of that program. A brief description of the testing methods, specimens, equipment, and procedures illustrates the similarities and differences in tests conducted at each laboratory. The data obtained from tests conducted in steam and utilizing test specimens with internal heaters or specimens containing alumina mandrels or pellets were compared for heating rates of 5, 28, and 55 C/sec. Both burst pressure and circumferential failure strain data versus burst temperature were plotted and compared in the range of 650 to 1250 C. It was found that testing methods, specimen oxidation layer, and irradiation effected the transient-heating burst test data.