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Enthalpy measurement and evaluation of heat capacity on (U, Pu)O$$_{2}$$

(U,Pu)O$$_{2}$$のエンタルピー測定と比熱評価

森本 恭一 ; 小笠原 誠洋*

Morimoto, Kyoichi; Ogasawara, Masahiro*

MOXの比熱は熱伝導率の評価や原子炉の過渡事象及び過酷事故の評価において重要となる熱物性値の一つである。本試験ではPuO$$_{2}$$とUO$$_{2}$$の影響が同程度に現れると考えられるPu含有率が約50%のMOX試料を用いて、エンタルピーの測定と比熱の評価を行った。試料はUとPu濃度をそれぞれ約50%に調整した硝酸溶液をマイクロ波脱硝で転換した粉末を用い、これを焼結してO/Mを2.00に調整したものである。この試料についてドロップカロリーメータを用いて2000K以上の高温領域でのエンタルピー測定を実施した。また、試料とタングステン製容器の反応を抑制するために測定ではレニウム製内容器を使用した。エンタルピーは温度に対し1900K辺りまでは一定の割合で上昇し、これ以上ではその上昇割合が大きくなった。これは比熱が1900K以上では上昇することを示す。

The heat capacity of MOX fuel is one of important thermophysical properties for the evaluation of its thermal conductivity and for the evaluations of transient event and severe accident of nuclear reactor. In this study, MOX sample with Pu-content of nearly 50% (50%Pu-MOX) was measured because it was predicted that the influence of Pu addition appeared to be significant. The raw material powder was cold-pressed and was sintered to make pellet. The oxygen to metal ratio of this pellet was adjusted to 2.00. The enthalpy of this sample was measured with drop calorimeter in in high temperature range. The rhenium container was used to prevent the reaction between the sample and the sample container. It was found that the enthalpy increased at a nearly constant rate up to about 1900 K with increasing temperature and that its rate rose at about 1900 K or more. It means that the heat capacity is approximately constant up to 1900K and starts to rise at about 1900K.

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