Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
POST-IRRADIATION EXAMINATION OF THE FUEL ROD CART-C1 N° 4
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Post-irradiation Examination of the Fuel Rod CART-C1
Author: A. FrigoPublisher:
ISBN:
Category :
Languages : en
Pages : 41
Book Description
Nuclear Science Abstracts
Author: Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 860
Book Description
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 Oconee 1 Fuel - Cycle 1 Destructive Test Phase
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Standard B and W Mark-B (15 x 15) pressurized water reactor fuel rods were destructively examined after one cycle of irradiation in the Oconee 1 reactor. Fuel rod average burnup ranged from 10,603 to 11,270 MWd/mtU for the rods examined. Data obtained included fuel rod extraction loads, rod dimensional changes, cladding tensile properties, fuel pellet gap length, fission product distribution, fission gas and crud composition, fuel densification, chemical burnup analysis, and fuel and cladding microstructure. As expected, parametric changes were well within the design envelope. Superficial corrosion and wear were found at spacer grid contact points. However, the 19 rods examined were structurally sound and exhibited no indications of cladding defects associated with pelletcladding interactions.
Accessions of Unlimited Distribution Reports
Author: Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 78
Book Description
Postirradiation Examination Results for the Irradiation Effects Test IE-1
Author: Arthur S. MehnerPublisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 266
Book Description
Post-irradiation examination procedures document. receiving and identification of full-length LWR fuel rods in universal cell-3
Author: R. J. ChenierPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Post-irradiation examination procedures document. scanning of nuclear fuel rods for gross and isotopic gamma activity
Author: R. R. ElderPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Post-irradiation examination procedures document. procedures for the puncturing of fuel rods, collection of fission gases, and void volume determination using the fcv1000
Author: J. MontinPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
