111 新型高温ガス冷却原子炉用燃料用ZrC被覆層のTEM・STEM観察(III)(超塑性と材料および造形法,オーガナイズドセッション)

概要

論文の詳細を見る
Japan Atomic Energy Agency (JAEA) has started to study and develop ZrC coated fuel particles for advanced high temperature gas cooled reactors (HTGRs). The ZrC coating layers were fabricated with bromide process at JAEA. We report in this study the microstructural change of the ZrC coating layers with heat treatment. We already reported the microstructures of as-fabricated ZrC coating layers last year. ZrC coated particles were annealed at about 1800℃ for 1 hour to simulate the sintering process of the real HTGR fuel. With annealing, ZrC grains were slightly grown especially near the surface regions and kept their orientation. The free carbons and/or voids cohered at the grain boundaries. The cohered free carbons and/or voids were appeared to form the clods of the free carbon ribbons. In addition, IPyC/ZrC boundary structure changed. Fibrous carbon texture was found at IPyC/ZrC boundary even in the specimen of the batch of which that texture was not observed in the as-fabricated specimen.
社団法人日本機械学会の論文
2008-09-12