Author: Atomic Energy of Canada LimitedPublisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Post Irradiation Examination of Seven Element Zircaloy-sheathed UOÒ Fuel Bundles Irradiated in Pressurized Water : Test CR-V-E
Author: Atomic Energy of Canada LimitedPublisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Post-irradiation examination of a co-extruded u3si-zircaloy fuel element irradiated in a defected condition
Author: K. D. CotnamZircaloy-2 sheathed uo2 irradiated at varying power levels - post irradiation examination of fuel
Author: A. S. BainPOST-IRRADIATION EXAMINATION OF ZIRCALOY-2- AND INCOLOY-800-CLAD FUEL RODS IRRADIATED TO 7000 MWD/TU IN THE CONSUMERS BIG ROCK POINT REACTOR.
Author: V. E. HazelPost-irradiation examination of two uo2-zr cermet fuel elements sheathed in zircaloy-4
Author: J. L. ConversiPostirradiation Examination Results for the Irradiation Effects Test Series IE-ST-2, Rod IE-002. [PWR].
![Postirradiation Examination Results for the Irradiation Effects Test Series IE-ST-2, Rod IE-002. [PWR]. PDF](https://books.google.com/books/content/images/frontcover/Txz2wQEACAAJ?fife=w80-h100)
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A postirradiation examination was conducted on a zircaloy-clad, UO2-fueled, pressurized water reactor (PWR) type rod which had been tested in the Power Burst Facility as part of the Irradiation Effects Test Series of the Thermal Fuels Behavior Program. The fuel rod, previously irradiated to a burnup of 15,800 MWd/t was subjected to a power ramp from 28 to 55 kW/m peak power at an average ramp rate of 4 kW/m/min. Posttest fuel restructuring and relocation, fission product redistribution, and fuel rod cladding deformation were evaluated and analyzed.
Pressure Testing of Zircaloy Tubing
Author: L. F. CochrunPublisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 44
Book Description
The post-irradiation examination of a 21-element, uo2 fuel bundle irradiated in WR-1
Author: J. F. WalkerFinal Report
Author: J. W. WeberIrradiation 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.