Author: D. N. SahPublisher:
ISBN:
Category :
Languages : en
Pages : 14
Book Description
Metallographic Examination of Irradiated Nuclear Fuel Elements at Radiometallurgy Hot Cell Facility
Author: D. N. SahThe Metallographic Examination of Irradiated Fuel Elements
Author: United Kingdom Atomic Energy AuthorityPublisher:
ISBN:
Category : Metallography
Languages : en
Pages :
Book Description
Metallographic Examination of Damaged N Reactor Spent Nuclear Fuel Element SFEC5,4378
Author: Metallography of Irradiated UO2-containing Fuel Elements
Author: W. K. BarneyPublisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 64
Book Description
Metallographic examination of four fuel elements from the fdo-716 irradiation
Author: D. A. LeachMetallographic Examination of Zircaloy-2 Sheathed Uranium Dioxide Fuel Elements Irradiated at High Heat Ratings
Author: G. W. ParryExamination of Irradiated EBWR Core-I Fuel Elements
Author: C. F. ReinkePublisher:
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.
Metallography of Irradiated UO$sub 2$-CONTAINING Fuel Elements
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A description of hot laboratory metallography and techniques of operation are presented. These facilities and techniques provided a means of examining fuel elements that contain UO/sub 2/ after irradiation to high burnups. Some unusual irradiation characteristics of UO/sub 2/ were observed, and each effect is discussed. A complete explanation of the causes of such effects has not yet been obtained. (auth).
Irradiation Testing of Tubular Fuel Elements
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 76
Book Description
This report discusses Zircaloy-2 clad uranium and uranium-2 weight percent zirconium fuel tubes which were irradiated to 3200 MWD/T in a high temperature water cooled loop. The outer clad of one tube split due to swelling of the uranium. Postirradiation examination of the fuel cores included metallography, electron microscopy, density determinations, dimensional measurements, and radiochemical burn-up analysis.
Evaluation of Irradiated Experimental OMR Fuel Elements
Author: J. H. WalterPublisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 54
Book Description