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Author : J. H. Walter
Publisher :
ISBN 13 :
Total Pages : 64 pages
Book Rating : 4.:/5 (319 download)
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:
Author : J. H. Walter
Publisher :
ISBN 13 :
Total Pages : 54 pages
Book Rating : 4.3/5 (91 download)
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:
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).
Author :
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ISBN 13 :
Total Pages : 1038 pages
Book Rating : 4.0/5 ( download)
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1965-03 with total page 1038 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 7 pages
Book Rating : 4.3/5 (91 download)
Download or read book Irradiation Evaluation of Fuel Elements for the PBRE and AVR Reactors written by and published by . This book was released on 1964 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : R. J. Sullivan
Publisher :
ISBN 13 :
Total Pages : 42 pages
Book Rating : 4.3/5 (91 download)
Download or read book Post-irradiation Examination of Surface Film Formation on OMRE Driver Element No. 219 written by R. J. Sullivan and published by . This book was released on 1964 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : R. F. Makens
Publisher :
ISBN 13 :
Total Pages : 484 pages
Book Rating : 4.3/5 (91 download)
Download or read book Organic Coolant Summary Report written by R. F. Makens and published by . This book was released on 1964 with total page 484 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 310 pages
Book Rating : 4.3/5 (91 download)
Download or read book Proceedings of the Organic Cooled Reactor Forum, October 6-7, 1960 written by and published by . This book was released on 1960 with total page 310 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
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ISBN 13 :
Total Pages : 1328 pages
Book Rating : 4.3/5 ( download)
Download or read book Nuclear Safety written by and published by . This book was released on 1959 with total page 1328 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 10 pages
Book Rating : 4.:/5 (685 download)
Download or read book Production Test IP-654-A Evaluation of Ten-inch Enriched Uranium Fuel Elements written by and published by . This book was released on 1964 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: At this present time, fuel elements of two basic lengths are used in the IPD reactors --a ''six-inch'' enriched uranium element (0.947 w/o U-235) and an ''eight-inch'' natural uranium element. Although fuel element diameters vary fro model to model, the length of the uranium cores is reasonably constant. An evaluation of fuel element lengths has bee made and the economic incentive for producing and irradiating longer fuel elements is fairly large. This test is a first step in evaluating the irradiation behavior of a new fuel model. The objective of the production test detailed in this report is to evaluate the irradiation behavior of ''ten-inch'' enriched (0.947 w/o U-235) uranium fuel elements.
Author :
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ISBN 13 :
Total Pages : 200 pages
Book Rating : 4.:/5 (31 download)
Download or read book U.S. Government Research Reports written by and published by . This book was released on 1960 with total page 200 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Bureau of National Affairs (Arlington, Va.)
Publisher :
ISBN 13 :
Total Pages : 1828 pages
Book Rating : 4.3/5 (91 download)
Download or read book Atomic Industry Reporter: Technology reports written by Bureau of National Affairs (Arlington, Va.) and published by . This book was released on 1955 with total page 1828 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Richard J. Burian
Publisher :
ISBN 13 :
Total Pages : 82 pages
Book Rating : 4.3/5 (91 download)
Download or read book Postirradiation Examination and Evaluation of an OMRE Fuel Assembly written by Richard J. Burian and published by . This book was released on 1959 with total page 82 pages. Available in PDF, EPUB and Kindle. Book excerpt: A fuel-element assembly from the first loading of the OMRE was examined in detail after experiencing an average uranium burnup of between 1 and 2 at.%. The rate of decay heat generation was evaluated by temperature monitoring of the shipping-cask coolant. Temperatures of the fuel-element-box assembly and the fuel plates were measured with thermocouples and tempilstiks. Structurally, the fuel-element assembly was affected very little by either radiation or the organic coolant-moderator. Although there was some distortion in the side and end plates of the assembly, the coolant channels between the fuel plates were free from major fouling and obstructions. The channel cross sections were reduced at specific points less than 5 per cent. The plates studied were subjected to complete gamma scanning. Specimens removed from selected areas of the scanned plates were radiochemically analyzed for burnup and the results correlated with the gamma-scan data. Burnup profiles were constructed for each of the scanned plates. The gamma-scan data were also utilized to determine the average plate burnup. (auth).
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).
Author : C. F. Reinke
Publisher :
ISBN 13 :
Total Pages : 38 pages
Book Rating : 4.3/5 (91 download)
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.
Author : J. L. Ballif
Publisher :
ISBN 13 :
Total Pages : 88 pages
Book Rating : 4.:/5 (319 download)
Download or read book Engineering Evaluation of a Mixed Alloy Fuel Element Irradiated at Elevated Temperatures in the SRE written by J. L. Ballif and published by . This book was released on 1960 with total page 88 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : R. M. Crawford
Publisher :
ISBN 13 :
Total Pages : 34 pages
Book Rating : 4.3/5 (91 download)
Download or read book Fabrication of Uranium Alloy Fuel Elements for OMRE Fourth Core written by R. M. Crawford and published by . This book was released on 1963 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:
