Development of the Ultra-microhardness Technique for Post Irradiation Examination of Fuel Cladding Tubes
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概要
- 論文の詳細を見る
Hardness measurements are potentially valuable for a quantitative discussion of embrittlement in the inner portions of fuel cladding tubes. The size of the indentation, however, is not negligible compared to the measuring region, even when a micro Vickers hardness tester is employed. This limits the measuring technique, and very little has been studied about degradation phenomena in the inner portion of the tubes.<BR>A hardness measurement system, equipped with a depth-sensing indentation instrument, and the necessary post irradiation examination technique for specimens with high radioactivity were successfully developed and the following observations were obtained from the systems application example. The diffusion coefficient of oxygen obtained from the hardness of an unirradiated zirconium lined cladding with simulated oxidation in the fuel rod showed good agreement with literature data. The calculated diffusion coefficient from hardness in the inner portion of irradiated Zircaloy-2 fuel rods was almost the same value as that of unirradiated zirconium, which implied that neither neutron irradiation nor fission fragment bombardment enhanced the oxygen diffusion in the inner portion of cladding tube.
- 社団法人 日本原子力学会の論文
- 1998-05-25
著者
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Nakatsuka Masafumi
Nippon Nuclear Fuel Development Co. Ltd.
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NOMATA Terumitsu
Isogo Engineering Center, Toshiba Corporation
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UMEHARA Hajime
Hitachi Works. Hitachi Ltd.
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Nomata Terumitsu
Isogo Engineering Center Toshiba Corporation
関連論文
- Annealing Study on Neutron Irradiation Effects in Resonance Frequencies of Zircaloy Plates by EMAR Method
- Interpretation of Acoustic Parameters Obtained by EMAR Measurement for Non-destructive Hydrogen Concentration Measurement in Zr Alloy
- A New Non-destructive Technique for Hydrogen Level Assessment in Zirconium Alloys using EMAR Method
- Development of the Ultra-microhardness Technique for Post Irradiation Examination of Fuel Cladding Tubes
- Stress Reorientation of Hydrides in Recrystallized Zircaloy-2 Sheet
- Measurements of friction coefficient and strain concetration of barriered fuel claddings under mechanical interaction with pellets.
- Reduction of plastic anisotropy of zircaloy cladding by neutron irradiation. (I). Yield loci obtained from knoop hardness.:Yield Loci Obtained from Knoop Hardness
- Effect of oxygen content on tensile properties of low oxygen zircaloy-2.
- Reduction of plastic anisotropy of zircaloy cladding by neutron irradiation. (II). Numerical simulations of yield loci.:Numerical Simulations of Yield Loci
- Effect of iodine on fatigue properties of zircaloy-2 fuel cladding under cyclic tensile stress.