Published 2005 | Version v1
Computer medium

Post-irradiation annealing test of high burnup UO2 fuel

  • 1. Korea Atomic Energy Research Inst., Yuseong, Daejeon (Korea, Republic of)

Description

To investigate the behavior of the fission gases in a high burnup UO2 fuel, PIA (Post Irradiation Annealing) test was performed. The highest burnup fuel, which was irradiated in Ulchin Unit 2, was transported to KAERI for the PIE. Non-destructive and destructive post irradiation test such as burnup analysis, pellet density change and detailed microstructure analysis by optical microscopy, SEM and EPMA were performed to confirm the fuel characteristics. By using the controlled oxidation technique, fission gas inventory could be distinguished grain boundary from grain matrix. From the preliminary test results, preferential oxidation of grain boundary was detected and confirmed by SEM image which showed separation of grain boundary. In addition, by the temperature elevation and longer oxidation time, Sharp re-increase of Kr-85 release was measured which released from grain matrix and confirmed by SEM also. The first PIA test result shows that about 40% to total residual fission gases were released from grain boundary. (author)

Part of:
Proceedings of the 2005 water reactor fuel performance meeting

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan
Imprint Place
Tokyo (Japan)
Imprint Title
Proceedings of the 2005 water reactor fuel performance meeting
Imprint Pagination
[1236 p.]
Journal Page Range
[5 p.]

Conference

Title
2005 water reactor fuel performance meeting
Dates
2-6 Oct 2005
Place
Kyoto (Japan)

Optional Information

Notes
This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH and UNIX; Acrobat Reader is included; Data in PDF format, Folder Name papers, Paper ID1031.pdf; 6 refs., 9 figs.