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Examination Of Irradiated Ebwr Core 1 Fuel Elements
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Book Synopsis Examination of Irradiated Ebwr Core-1 Fuel Elements by :
Download or read book Examination of Irradiated Ebwr Core-1 Fuel Elements written by and published by . This book was released on 1960 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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).
Book Synopsis Examination of Irradiated EBWR Core-I Fuel Elements by : C. F. Reinke
Download or read book Examination of Irradiated EBWR Core-I Fuel Elements written by C. F. Reinke and published by . This book was released on 1960 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis Evaluation of Irradiated OMRE Fuel Elements First Core Loading by : J. H. Walter
Download or read book Evaluation of Irradiated OMRE Fuel Elements First Core Loading written by J. H. Walter and published by . This book was released on 1960 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Examination of EBWR Core-1A Fuel by : R. Carlander
Download or read book Examination of EBWR Core-1A Fuel written by R. Carlander and published by . This book was released on 1966 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis Evaluation of Irradiated Experimental OMR Fuel Elements by : J. H. Walter
Download or read book Evaluation of Irradiated Experimental OMR Fuel Elements written by J. H. Walter and published by . This book was released on 1960 with total page 54 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Examination of an Irradiated Prototype Fuel Element for the Elk River Reactor by : L. A. Neimark
Download or read book Examination of an Irradiated Prototype Fuel Element for the Elk River Reactor written by L. A. Neimark and published by . This book was released on 1961 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Reactor Materials written by and published by . This book was released on 1961 with total page 1094 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1974 with total page 764 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Core Materials written by and published by . This book was released on 1959 with total page 844 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis EVALUATION OF IRRADIATED EXPERIMENTAL OMR FUEL ELEMENTS--1 by :
Download or read book EVALUATION OF IRRADIATED EXPERIMENTAL OMR FUEL ELEMENTS--1 written by and published by . This book was released on 1960 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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).
Book Synopsis Water Chemistry and Fuel Element Scale in EBWR by : C. R. Breden
Download or read book Water Chemistry and Fuel Element Scale in EBWR written by C. R. Breden and published by . This book was released on 1960 with total page 112 pages. Available in PDF, EPUB and Kindle. Book excerpt: The first two sections summarize investigations in EBWR concerned with some aspects of water chemistry. The results of many of these investigations have not been previously published in a form given wide distribution. Included are studies of water conditions, corrosion products (composition, activities, transportation, deposition, and distribution), water dissociation, water activity, fission-product release, and build-up of plant activity.
Book Synopsis Government-wide Index to Federal Research & Development Reports by :
Download or read book Government-wide Index to Federal Research & Development Reports written by and published by . This book was released on 1965 with total page 954 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Scientific and Technical Aerospace Reports by :
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1971 with total page 1330 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis National Symposium on Developments in Irradiation Testing Technology by :
Download or read book National Symposium on Developments in Irradiation Testing Technology written by and published by . This book was released on 1969 with total page 804 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Summary Report on Irradiation of Prototype EBR-II Fuel Elements by : J. H. Monaweck
Download or read book Summary Report on Irradiation of Prototype EBR-II Fuel Elements written by J. H. Monaweck and published by . This book was released on 1960 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis Nondestructive Examination of 51 Fuel and Reflector Elements from Fort St. Vrain Core Segment 1 by :
Download or read book Nondestructive Examination of 51 Fuel and Reflector Elements from Fort St. Vrain Core Segment 1 written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fifty-one fuel and reflector elements irradiated in core segment 1 of the Fort St. Vrain High-Temperature Gas-Cooled Reactor (HTGR) were inspected dimensionally and visually in the Hot Service Facility at Fort St. Vrain in July 1979. Time- and volume-averaged graphite temperatures for the examined fuel elements ranged from approx. 400° to 750°C. Fast neutron fluences varied from approx. 0.3 x 1025 n/m2 to 1.0 x 1025 n/m2 (E> 29 fJ)/sub HTGR/. Nearly all of the examined elements shrank in both axial and radial dimensions. The measured data were compared with strain and bow predictions obtained from SURVEY/STRESS, a computer code that employs viscoelastic beam theory to calculate stresses and deformations in HTGR fuel elements.
Book Synopsis Postirradiation Examination of EBR-I Core -IV Prototype Fuel Rods by : R. Carlander
Download or read book Postirradiation Examination of EBR-I Core -IV Prototype Fuel Rods written by R. Carlander and published by . This book was released on 1963 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt: Four EBR-I Mark-IV prototype fuel rods containing slugs of plutonium- 1 wt% aluminum alloy were irradiated in the EBR-I reactor at central fuel temperatures from 342 to 386 deg C and at burnups up to 0.1 at.%. No appreciable slumping of the fuel occurred during irradiation, and no significant density nor dimensional changes were observed. Variation of the initial fuel-cladding annulus from 0.004 to 0.019 in. had no significant effect on the slumping behavior, but the larger clearance did allow the fuel pin to bow to a greater extent than that observed in fuel rods with smaller annuli. A niobium restrainer effectively decreased the amount of bowing from that found in a rod with a similar annulus, but did not appear to offer any greater restriction than that provided by a small 0.004-in. annulus.
