Toward a more reliable evaluation of fuel fracture during LOCA
Author:
Affiliation:
1. 日本原子力研究開発機構
Publisher
Atomic Energy Society of Japan
Subject
Nuclear Energy and Engineering
Link
https://www.jstage.jst.go.jp/article/jaesjb/63/11/63_780/_pdf
Reference12 articles.
1. 1) T. Narukawa et al., Experimental and statistical study on fracture boundary of non-irradiated Zircaloy-4 cladding tube under LOCA conditions, J. Nucl. Mater., Vol. 499, pp. 528-538, 2018.
2. 2) T. Narukawa et al., Uncertainty quantification of fracture boundary of pre-hydrided Zircaloy-4 cladding tube under LOCA conditions, Nucl. Eng. Des., Vol. 331, pp. 147-152, 2018.
3. 3) T. Narukawa, M. Amaya, Oxidation behavior of high-burnup advanced fuel cladding tubes in high-temperature steam, J. Nucl. Sci. Technol., Vol. 56, No. 7, pp. 650-660, 2019.
4. 4) T. Narukawa, M. Amaya, Fracture limit of high-burnup advanced fuel cladding tubes under loss-of-coolant accident conditions, J. Nucl. Sci. Technol., Vol. 57, No. 1, pp. 68-78, 2020.
5. 5) T. Narukawa, M. Amaya, Four-point-bend tests on high-burnup advanced fuel cladding tubes after exposure to simulated LOCA conditions, J. Nucl. Sci. Technol., Vol. 57, No. 7, pp. 782-791, 2020.
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