Transient cooling process of fuel rod in reactivity initiated accident.

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概要

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• Out-of-pile experiments were performed with Zircaloy-4 rods in subcooled water envi-ronment to study the basic phenomena occurring in the transient cooling process undergone by a fuel rod during a reactivity-initiated accident (RIA) affecting a light water reactor (LWR). The experimental results show that the cooling process of the fuel rod during an RIA can be divided into three phases separated by the quenching temperature <I>T<SUB>q</SUB></I> and the rewetting temperature <I>T<SUB>r</SUB></I>. <BR>It is also noted from the experimental results that with increasing degree of subcool-ing, <I>T<SUB>q</SUB></I> tends to rise to levels far exceeding the maximum liquid superheat temperature of water ; <I>T<SUB>r</SUB></I>, on the other hand, is little affected by the cooling water temperature, and remains close to that of the maximum superheat temperature. <BR>Numerical calculations indicate conclusively that radial heat transfer to coolant water is the dominant factor that governs the transient cooling process in an RIA affecting the cold start-up of a BWR, rather than the axial heat conduction through rod which is con-sidered to be the basic mechanism of cooling that governs the reflooding process during a LOCA.

• 一般社団法人 日本原子力学会の論文

著者

• MORI Michitsugu

  Nuclear Power R&D Center, Tokyo Electric Power Co.

• TODA Saburo

  Nuclear Engineering Department, Tohoku University

• OCHIAI Masa-aki

  Ship Research Institute

• SAITO Shinzo

  Division of Reactor Safety, Japan Atomic Energy Research Institute

• MORI Michitsugu

  Nuclear Engineering Department, Tohoku University

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