A science‐based mixed oxide property model for developing advanced oxide nuclear fuels

Author:

Kato Masato1234ORCID,Oki Takumi2,Watanabe Masashi1234ORCID,Hirooka Shun23,Vauchy Romain2,Ozawa Takayuki23,Uwaba Tomoyuki4,Ikusawa Yoshihisa2,Nakamura Hiroki5,Machida Masahiko5

Affiliation:

1. Nuclear Plant Innovation Promotion Office Japan Atomic Energy Agency Oarai‐machi Japan

2. Fuel Engineering Department, Plutonium Fuel Development Center Japan Atomic Energy Agency Tokai‐mura Japan

3. Fuel Cycle Design Office Japan Atomic Energy Agency Oarai‐machi Japan

4. Fuels and Materials Department, Oarai Research and Development Center Japan Atomic Energy Agency Oarai machi Japan

5. Center for Computational Science and e‐Systems Japan Atomic Energy Agency Kashiwa‐shi Japan

Abstract

AbstractHerein, a science‐based uranium and plutonium mixed oxide (MOX) property model is derived for determining the properties of MOX fuel and analyzing their performance as functions of Pu content, minor‐actinide content, oxygen‐to‐metal ratio, and temperature. The property model is constructed by evaluating the effect of phonons and electronic defects on the heat capacity and thermal conductivity of MOX fuels. The effect of phonons was evaluated based on experimental datasets related to lattice parameters, thermal expansion, and sound speeds. Moreover, the effect of electronic defects was determined by analyzing oxygen‐potential data based on defect chemistry. Furthermore, the model evaluated the effect of the Bredig transition on the thermal properties of MOX fuel by analyzing the irradiation test results. The derived property model is applied to the performance code to analyze fast reactor fuel pins.

Publisher

Wiley

Subject

Materials Chemistry,Ceramics and Composites

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