Effect of fuel pellet eccentricity with cladding on fuel rod thermal behavior under reactivity initiated accident condition.
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概要
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Fuel rod behavior under Reactivity Initiated Accident (RIA) conditions has been studied in the Nuclear Safety Research Reactor (NSRR), JAERI. In the experiments, cladding thermal behavior was observed to be influenced by the fuel pellet eccentricity to produce large azimuthal temperature variation in the cladding. The maximum azimuthal cladding temperature difference was measured to be as large as 150°C by thermocouples attached to opposite sides of the cladding around the circumference, though the thermocouples did not always detect the maximum temperature difference around the circumference. The actual temperature differences in the fuel rods subjected to less than 290 cal/g•UO<SUB>2</SUB> were estimated to be 350°C at maximum based on metallographies. A simple calculation considering gap conductance variations also showed that the maximum tempera-ture difference became 350°C under fully eccentrical condition in the fuel rod subjected to 260 cal/g•UO<SUB>2</SUB>. Moreover, as the rod damage such as cladding deformation, melting and failure occurs unevenly around the circumference due to the fuel pellet eccentricity in general, the fuel pellet eccentricity should influence the fuel rod failure under RIA condi-tions.
- 一般社団法人 日本原子力学会の論文
著者
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SAITO Shinzo
Division of Reactor Safety, Japan Atomic Energy Research Institute
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SHIOZAWA Shusaku
Division of Nuclear Safety Research, Japan Atomic Energy Research Institute
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YANAGIHARA Satoshi
Division of Nuclear Safety Research, Japan Atomic Energy Research Institute
関連論文
- Transient cooling process of fuel rod in reactivity initiated accident.
- Effect of fuel pellet eccentricity with cladding on fuel rod thermal behavior under reactivity initiated accident condition.
- Measurement and evaluation on pulsing characteristics and experimental capability of NSRR.