UID:
almafu_9958103797102883
Format:
1 online resource (548 pages)
ISBN:
1-280-35699-5
,
9786610356997
,
92-64-01158-7
Series Statement:
Nuclear science
Content:
This report communicates the results of an international seminar which reviewed recent progress in the field of pellet-clad interaction in light water reactor fuels. It also draws a comprehensive picture of current understanding of relevant phenomena and their impact on the nuclear fuel rod, under the widest possible conditions. State-of-the-art knowledge is presented for both uranium-oxide and mixed-oxide fuels.
Note:
"NEA No. 6004."
,
Foreword; CONTENTS; Executive Summary; SESSION I Opening and Industrial Goals; SESSION II Fuel Material Behaviour in PCI Situation (Part 1); Fuel Material Behaviour in PCI Situation (Part 2); SESSION III Cladding Behaviour Relevant to PCI; SESSION IV In-pile Rod Behaviour; SESSION V Modelling of the Mechanical Interaction Between Pellet and Cladding (Part 1); Session V Modelling of the Mechanical Interaction Between Pellet and Cladding (Part 2); List of Participants
,
English
Language:
English
