Examination of an Irradiated Prototype Fuel Element for the Elk River Reactor PDF Download
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Author: L. A. Neimark Publisher: ISBN: Category : Boiling water reactors Languages : en Pages : 42
Book Description
An examination was made of a prototype Elk River Reactor fuel element irradiated in the EBWR to a maximum burn-up of 1000 Mwd(t). The assembly, which consisted of an array of type 304 stainless-steel tubes fueled with pellets of 97 wt.% ThO2-3 wt.% UO2, showed insignificant dimensional changes. Irregular vertical packing of the fuel pellets gave a "banded" appearance to the fuel rods because of preferential oxide deposition. The brazing material used in the center strap of the assembly showed noticeable corrosion effects. The fuel pellets showed no themal effects and exhibited little cracking. The dimensional stability was excellent. The fuel exhibited good gas-retention characteristics.
Author: L. A. Neimark Publisher: ISBN: Category : Boiling water reactors Languages : en Pages : 42
Book Description
An examination was made of a prototype Elk River Reactor fuel element irradiated in the EBWR to a maximum burn-up of 1000 Mwd(t). The assembly, which consisted of an array of type 304 stainless-steel tubes fueled with pellets of 97 wt.% ThO2-3 wt.% UO2, showed insignificant dimensional changes. Irregular vertical packing of the fuel pellets gave a "banded" appearance to the fuel rods because of preferential oxide deposition. The brazing material used in the center strap of the assembly showed noticeable corrosion effects. The fuel pellets showed no themal effects and exhibited little cracking. The dimensional stability was excellent. The fuel exhibited good gas-retention characteristics.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
An examination was made of a prototype Elk River Reactor fuel element irradiated in the EBWR to a maximum burn-up of 1000 Mwd(t). The assembly, which consisted of an array of type 304 stainless-steel tubes fueled with pellets of 97 wt.% ThO2-3 wt.% UO2, showed insignificant dimensional changes. Irregular vertical packing of the fuel pellets gave a "banded" appearance to the fuel rods becase of preferential oxide deposition. The brazing material used in the center strap of the assembly showed noticeable corrosion effects. The fuel pellets showed no themal effects and exhibited little cracking. The dimensional stability was excellent. The fuel exhibited good gas-retention characteristics. (auth).
Author: C. F. Reinke Publisher: ISBN: Category : Nuclear fuel elements Languages : en Pages : 38
Book Description
Two fuel elements were removed from the Experimental Boiling Water Reactor and examined in a hot cell. The elements had maximum burn-ups of 0.11 and 0.39 at.%. Both were disassembled and sampled for the evaluation of the effects of in-pile operation and radiation damage to the fuel. The fuel elements were in good condition with no ruptured cladding, core-clad non-bonds, or excessive fuel-plate swelling or warpage. Thin samples cut from the fuel plates in element ET-51 warped and cracked, suggesting a relieving of locked-in stresses and indicating that after 0.39 at.% burn-up the fuel cores were hard, brittle, and highly stressed. The rate of fuel-plate volume increase owing to the burn-up of uranium was 6 to 7% DELTA V per at.% burn-up. Hydrogen was picked up by the fuel plates under reactor operating conditions with the probable formation of isolated areas of small amounts of zirconium hydride. Annealing studies on sections of fuel plate at 500 and 550 deg C indicated bulk volume increases of 1 to 2% and 5 to 10%, respectively, after 500 hr. A 600 deg C anneal resulted in a bulk volume increase of 17% after 45 hr.
Author: L. A. Neimark
Author: L. A. Neimark
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Author: T. J. Pashos
Author: Leonard E. Link
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Author: James M. Jacobs
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Author: C. F. Reinke