Reactor fuel rod

Tong, L. S., 1967b, Heat Transfer in Water-Cooled Nuclear Reactors, Nuclear Eng. Design (5 301. (3) Tong, L. S., 1968a, An Evaluation of the Departure from Nucleate Boiling in Bundles of Reactor Fuel Rods, Nuclear Sci. Eng. 33 7-15. (5)... 

Principal applications for radiography include the inspection of castings, electrical assemblies, weldments, small, thin, and complex wrought products, some nonmetallics. solid propellant rocket motors, cans or containers, composites, and nuclear reactor fuel rods, amoug many others. 

Gamma rays from spent reactor fuel rods were used for the photoreduction of the trivalent lanthanides. A spectral survey of these divalent containing crystals has been presented by McClure and Kiss (16). This photoreduction technique reduces only a minor fraction of the total trivalent concentration, and those divalent ions produced are unstable with respect to heat and/or light. Fong (3) has described these effects using divalent dysprosium as an example. 

Fast breeder reactor fuel rods consist of stainless-steel-clad mixed oxide (U,Pu)02 fuel however, more stable alloys for cladding and in-core structural materials, with resistance to swelling and embrittlement under fast neutron irradiation, and more efficient fuels (carbide see 17.3.12.1.2) or nitride (see 17.3.12.3)] are needed h The mechanical, metallurgical, and chemical processes in fuel element irradiation are depicted in Figure 1. Figure 2 shows the PFR (U.K.) fast breeder fuel element, and Figures 3 and 4 illustrate the Fast Flux Test Facility (FFTF) fuel system. 

L. S. Tong, An Evaluation of the Departure From Nucleate Boiling in Bundles of Reactor Fuel Rods, Nuclear Sci. Eng. (33) 7-15,1968. 

The use of the concept of confidence limits is widespread in industry. As a specific example, let us assume that x is the thickness of the cladding of a reactor fuel rod. The average (nominal) thickness is x . The reactor designer would like to be certain that a certain fraction of fuel rods will always have thickness within prescribed limits. Let us say that the designer desires a confidence limit of 99.87 percent. This means that no more than 13 rods out of... 

Steep temperature gradients are generated in reactor fuel rods during reactor operation. The temperature gradient thus created, in turn, induces diffusion of species—thermal diffusion—and the diffused species redistribute in the fuel rod. This redistribution, however, is caused by transport not only through the solid phase but also through the gas phase, which complicates the mechanisrn considerably 343). 

Bleier, A., Kroebel, R., Neeb, K. H., Schneider, E. Tritium inventories and behaviour in Zircaloy cladding of spent light-water reactor fuel rods. Proc. Intemat. Topical Meeting on Fuel Reprocessing and Waste Management, Jackson Hole, Wyoming, USA, 1984, Vol. 1, p. 238-248... 

Peehs, M., Manzel, R., Schweighofer, W., Haas, W., Haas, E., Wurtz, R. On the behaviour of cesium and iodine in light-water reactor fuel rods. J. Nucl. Materials 97, 157—164... 

The thickness of the corrosion product deposits on BWR fuel rods differs markedly from plant to plant, obviously depending on the iron concentration in the feedwater (which usually is below 10 ppb). Values on the order of a fewmg/cm were reported from some plants, whereas others showed layers of only 0.1 to 0.5mg/cm. The differences in layer thickness to PWRs (up to an order of magnitude) are mainly due to the fact that crud deposition on BWR fuel rods is supported by the boiling effect on the fuel rod surfaces. In the Soviet RBMK reactors, fuel rod deposits on the order of 40 to 60 pm are typical (according to Dragunov et al., 1992). 

N-1 Spacer Storage Silos Irradiated fuel spacers. The silos contained irradiated fuel spacers which came in contact with the reactor fuel rods. 

Recent experimental data suggest that high bumup fuel may be more prone to failure during design-basis transients and reactivity insertion accidents than previously thought. Tests on the relationship between fuel failure enthalpy and bumup for pressurized water reactor fuel rods indicate lower failure initiation enthalpy thresholds (measured in differential calories/gram) than was crmsidered in the evaluation of currently approved fuel bumup limits. 

Routine gas adsorption studies can often be used when the aim of the investigation is quality control of powder systems. In the late 1950 s I was involved in measuring the surface area of uranium dioxide powders using Krypton adsorption as a quality control method for the fabrication of nuclear reactor fuel rods. 

X-10] HAGRMAN, D.L., REYMAN, G.A., MATPRO-Versionl 1, A handbook of materials properties for use in the analysis of light water reactor fuel rod behaviour, NUREG/CR-0497, TREE-1280, Rev.3 (1979). 

J. Yoo, Y. Oka, Y. Ishiwatari and J. Liu, Thermo-Mechanical Analysis of Supercritical Pressure Light Water-Cooled Fast Reactor Fuel Rod by FEMAXI-6 Code , Annals of Nuclear Energy, Vol. 33(17), 1379-1390 (2006)... 

D. L. Hagrman and G. A. Reyman, MATPRO-Version 11. A Handbook of Materials Properties for Use in the Analysis of Light Water Reactor Fuel Rod Behavior, NUREG/CR-0497, TREE-1280, Rev. 3, US-NRC (1979)... 

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