Development of Fabrication Technology for Oxidation-Resistant Fuel Elements for High-Temperature Gas-Cooled Reactors

Author:

AIHARA Jun1,HONDA Masaki2,UETA Shohei1,OGAWA Hiroaki3,OHIRA Koichi2,TACHIBANA Yukio1

Affiliation:

1. Japan Atomic Energy Agency, Oarai Research and Development Center

2. Nuclear Fuel Industries, Ltd.

3. Japan Atomic Energy Agency, Tokai Research and Development Center

Publisher

Atomic Energy Society of Japan

Subject

Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference7 articles.

1. 1) M. Goto, Y. Inaba, H. Ohashi, H. Sato, Y. Fukuya, Y. Tachibana, Conceptual Design of Small-sized HTGR System (II) – Nuclear Design–, JAEA–Technology 2012–017, Japan Atomic Energy Agency, (2012), [in Japanese].

2. 2) F. Kobayashi, S. Shiozawa, K. Hayashi, K. Sawa, S. Sato, K. Fukuda, M. Kaneko, T. Sato, An Inspection Standard of Fuel for the High Temperature Engineering Test Reactor, JAERI–M 92–079, Japan Atomic Energy Agency, (1992), [in Japanese].

3. 3) K. Ikawa, T. Tobita, K. Iwamoto, Comparison in Water-Vapor Corrosion between Resin Bonded and Silicon Bonded Graphite Compacts, JAERI–M 7477, Japan Atomic Energy Agency, (1978), [in Japanese].

4. 4) K. Ikawa, Y. Kurata, K. Iwamoto, “Reaction hot pressing of graphite-silicon,” High Temp.-High Pressures, 9, 431–435 (1977).

5. 5) J. Aihara, M. Goto, Y. Inaba, S. Ueta, J. Sumita, Y. Tachibana, “Nuclear thermal design of high temperature gas-cooled reactor with SiC/C mixed matrix fuel compacts,” Proc. HTR 2016, Las Vegas, USA, Nov. 6–10, 2016, 814–822 (2016).

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