Published November 2016 | Version v1
Book

Post-irradiation Experiment on IG-110 and A3-3 Graphites for HTGR - 18494

  • 1. Advanced Nuclear Fuel Development Division, Kaeri, Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353, Korea (Korea, Republic of)

Description

The first irradiation test of A3-3 graphite matrix and IG-110 graphite were performed in Hanaro during the period of August 2013 through March 2014. The dimensional and weight changes, microstructure, and thermal diffusivity were investigated in different directions of the specimen after the irradiation. Interestingly, the density of the A3-3 matrix was increased by 9.4% due to the weight increase after the irradiation. Moreover, the thermal diffusivity in the radial direction of the A3-3 matrix is almost 3-times higher than that of the axial direction owing to the radially oriented graphite texture shown in the microstructure. Meanwhile, 10-20 #mu#m sized irradiation induced pores are observed in the microstructure of IG-110. The thermal diffusivity measurement of pre- and post-irradiated IG-110 results in a 68% irradiation-dominant decrease of thermal conductivity. (authors)

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park, IL (United States)
Imprint Pagination
6 p.

Conference

Title
International Topical Meeting on High Temperature Reactor Technology
Acronym
HTR 2016
Dates
6-10 Nov 2016
Place
Las Vegas, NV (United States)

Optional Information

Notes
8 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)