Author: M. R. FloydPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Post-irradiation examination of the second prototype low-void reactivity fuel bundle "ajr" irradiated in the NRU reactor
Author: M. R. FloydPost-irradiation examination of the first prototype low-void reactivity fuel bundle "ahx" irradiated in the NRU reactor
Author: M. R. FloydPost-irradiation examination of the first prototype low-void reactivity fuel bundle "ahx" irradiated in the NRU reactor
Author: M. R. FloydProposal for the irradiation of the second prototype low-void reactivity fuel bundle, two canflex geometry fuel bundles, and a materials test bundle in the s-239 string in the l-8 test section of the u-1 loop
Author: P. G. AndersonProposal for the irradiation of the second prototype low-void reactivity fuel bundle, two canflex geometry fuel bundles, and a materials test bundle in the s-236 string in the l-8 test section of the u-1 loop
Author: P. G. AndersonProposal for the continued irradiation of the second prototype low-void reactivity fuel bundle and a canflex geometry fuel bundle, in the s-243 string in the l-8 test section of the u-1 loop
Author: P. G. AndersonProposal for the continued irradiation of the second prototype low-void reactivity fuel bundle and a canflex geometry fuel bundle, in the s-242 string in the l-8 test section of the u-1 loop
Author: P. G. AndersonPost-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.
Author: C. G. Ouellet
Author: C. G. Ouellet