Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
POST-IRRADIATION EXAMINATION OF THE GAIL III-B FUEL ELEMENT.
Author: IRRADIATION TEST OF THE GAIL III-B FUEL ELEMENT IN THE GENERAL ATOMIC INPILE LOOP.
Author: Nuclear Science Abstracts
Author: Post-irradiation Examination Techniques for Research Reactor Fuels
Author: IAEAPublisher: International Atomic Energy Agency
ISBN: 920102021X
Category : Technology & Engineering
Languages : en
Pages : 149
Book Description
Post-irradiation examination (PIE) is an indispensable step in the selection of new or improved research reactor fuel, and in the characterization and understanding of its in-core behaviour. This publication provides an introduction to PIE techniques. It describes a typical PIE process from intercycle inspections in the reactor pool or channel, to hot cell PIE, which is subdivided into non-destructive and destructive testing techniques with their typical output, advantages and drawbacks, and their applicability to understanding fuel irradiation behaviour. Much of the work presented in this publication originated from the research and development of new low enriched uranium research reactor fuels. Intended readers include research reactor operators, regulators and their technical support organizations, fuel developers and manufacturers, laboratory staff, and policy makers.
Post Irradiation Examination of Elliptical Fuel Element (RM-416).
Author: W. J. GruberThe Post-irradiation Examination of the D7 (XPR-2) Fuel Element
Author: L.J. HankartPost-irradiation examination of x-609 phase ii fuel elements
Author: B. P. LeclairPost-irradiation Examination of U3Si{sub 1.6}-Al Dispersion Fuel Element LC04
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 16
Book Description
A low-enrichment uranium (LEU) irradiation test (SIMONE project) was performed in the 45 MW Petten High-flux Reactor (HFR) as part of the Reduced Enrichment for Research and Test Reactor (RERTR) program. An LEU U3Si{sub 1.6}-Al dispersion fuel element with a fuel loading of 5.5 g cm−3 was irradiated and performed well to a total burnup of 66% and a peak burnup of 85%. The swelling behavior of the fuel was similar to that observed in previous U3Si(subscript x) irradiation experiments. The resulting fuel plate thickness increases and associated changes in coolant channel cross-sections were well within acceptable limits.
Author: D. E. Teed
Author: R. J. Chenier