The Effects of Plutonium Content and Self-Irradiation on Thermal Conductivity of Mixed Oxide Fuel

Author:

Ikusawa Yoshihisa1ORCID,Morimoto Kyoichi1,Kato Masato2,Saito Kosuke1,Uno Masayoshi3

Affiliation:

1. Japan Atomic Energy Agency, 4-33 Muramatsu, Tokai-mura, Naka-gun, Ibaraki 319-1194, Japan

2. Japan Atomic Energy Agency, 4002 Narita-Cho, Oarai-machi, Higashiibaraki-gun, Ibaraki 311-1393, Japan

3. University of Fukui, Research Institute of Nuclear Engineering, 1-3-33 Kanawachou, Turuga-city, 914-0055 Japan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference13 articles.

1. Thermal conductivity of hypostoichiometric low Pu content (U,Pu)O2−x mixed oxide

2. Impact of auto-irradiation on the thermophysical properties of oxide nuclear reactor fuels

3. “Status and Advances in MOX Fuel Technology,” Technical Reports Series No. 415, International Atomic Energy Agency (2003).

4. T. OKITA et al. “Operational Experiences in MOX Fuel Fabrication for the FUGEN Advanced Thermal Reactor,” IAEA-SM-358/3, International Atomic Energy Agency (1999).

5. Y. IKUSAWA et al. “Post Irradiation Examination for the FUGEN High Burn-Up MOX Fuel Assembly (III) Final Report (Technical Document),” JNC TN8410 2005-012, Japan Nuclear Cycle Development Institute (Aug. 2005).

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