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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: 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: Publisher: ISBN: Category : Languages : en Pages :
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 gcod condition with no ruptured.cladding, core-clad nonbonds, 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 forraation of isolated areas of small announts of zirconiura 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. (auth).
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: R. Carlander Publisher: ISBN: Category : Alloys Languages : en Pages : 34
Book Description
AN EBWR fuel element was examined after the 100-MW operation and maximum burnup of 0.61 a/o, as part of a continuing evaluation of the in-reactor performance and irradiation damage of the fuel alloy. Although the maximum rate of volume increase per a/o burnup was 7.6% at the point of maximum burnup, increases as high as 13.3% per a/o burnup were found in regions of lower burnup. These larger rates of volume increase were due to a combination of burnup and high centerline fuel temperature. Large-scale buildups, particularly in regions free of nucleate boiling, contributed to the higher centerline fuel temperatures by acting as a thermal insulation barrier between the cladding and the water coolant. The temperatures, which were calculated to be in excess of 500 degrees C, resulted in an annealing out of the residual stresses that existed in the fuel elements before the 100-MW operation. The results indicate that for satisfactory performance at high power levels, the centerline fuel temperature of the fuel elements of the EBWR type should be maintained below 500 degrees C through the adequate control of scale accumulation.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
As part of a program to develop an economical fuel cycle for an Organic Moderated Reactor (OMR), experimental fuel elements are being irradiated in the Organic Moderated Reactor Experiment (OMRE). The first two experimental fuel elements have been removed from the OMRE, examined, and evaluated. These extended-surface, platetype fuel elements had finned aluminum cladding, metallurgically bonded to flat uranium alloy fuel plates. A 0.0005 in. nickel layer was used to prevent interdiffusion between the aluminum and uranium. The fuel core alloys irradiated were U--5.5% Mo and U--3.5% Mo--0.5% Si. These two experimental elements were removed from the reactor after one of the elements released fission products, and cladding temperatures increased on both fuel elements. The maximum measured cladding temperature was 780 deg F. The maximum fuel burnup was later determined to be 0.25 at.% U. Hot-cell examination revealed that the coolant inlet ends of the fuel elements had filtered particulate matter out of the coolant, which blocked the ends of the coolant channels. Restriction of the coolant flow through the elements caused partial melting of the cladding in one fuel element and a blister on one of the fuel plates from the other fuel element. Dimensions were taken on three of the fuel plates. Metallographic sections from the blistered fuel plates were examined, and burnup profiles were determined for the three plates measured. The fuel had good dimensional stability, which is significant, since the melted cladding and the core microstructure evidenced temperatures substantially above the maximurn temperatures recorded by thermocouples. Nothing was observed that would indicate the fuel elements would not have functioned properly in the same coolant if the coolant were free of particulate matter of sizes that could be trapped. (auth).
Author: J. H. Monaweck Publisher: ISBN: Category : Breeder reactors Languages : en Pages : 36
Book Description
This report summarizes the series of irradiations performed in the CP-5, MTR, and ETR on promising prototype EBR-II fuel elements. The exposure history and the effects of irradiation are described and illustrated photographically. These include dimensional and density changes, fission gas buildup, and fission product contamination of the sodium thermal bond, as a function of fuel burnup and operating temperature. The lesser physical changes evidenced by the stainless steel-clad uranium-fissium alloy support its superiority over the zirconium-uranium alloy, and ultimate selection for the initial core loading of the EBR-II.
Author: Publisher: ISBN: Category : Languages : en Pages : 5
Book Description
This report discusses two of the direct cast core I & E fuel elements irradiated in C Reactor under PT-IP-93 which were received at the Radiometallurgy Laboratory for examination during July 1959. One of the elements was badly warped and distorted while the other of the same series had remained relatively unchanged. Both pieces had received an average exposure of 689 MWD/T. Warp and diameter measurements show that the one element had warped approximately .040 in. and had become distorted in two longitudinal planes at the male end. The distortion planes are at right angles which gives the transverse section a square a appearance. A comparison of the grain size from three positions along the warped element with a section cut from the unwarped element revealed a greater number of large grains in the zones of highest distortion. The maximum size grains, were in the order of 2.5 mm -- 3.8 mm vs normal .2 mm. Also prevalent in all sections examined vas a columnar type grain structure around the outside periphery. It is evident that the pre-irradiation heat treatment failed to refine the grain size sufficiently to prevent nonuniform growth of this element during irradiation. A corrosion pit was noticed in the canwall of the second element that had penetrated of the canwall.
Author: C. F. Reinke
Author: C. F. Reinke
Author: 
Author: J. H. Walter
Author: L. A. Neimark
Author: R. Carlander
Author: 
Author: T. J. Slosek
Author: J. H. Monaweck
Author: J. H. Walter
Author: