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Improved-EDC tests on the Zircaloy-4 cladding tube with an outer surface pre-crack

外面予き裂入りジルカロイ4被覆管の改良EDC試験

篠崎 崇*; 宇田川 豊  ; 三原 武  ; 杉山 智之 ; 天谷 政樹  

Shinozaki, Takashi*; Udagawa, Yutaka; Mihara, Takeshi; Sugiyama, Tomoyuki; Amaya, Masaki

In order to investigate the failure behavior of fuel cladding under a reactivity-initiated accident (RIA) condition, biaxial stress tests on unirradiated Zircaloy-4 cladding tube with an outer surface pre-crack were carried out under room temperature conditions by using an improved Expansion-Due-to-Compression (improved-EDC) test method which was developed by Japan Atomic Energy Agency (JAEA). The specimens with an outer surface pre-crack were prepared by using RAG (Rolling After Grooving) method. In each test, a constant longitudinal tensile load of 0, 5.0 or 10.0 kN was applied along the axial direction of specimen, respectively. All specimens failed during the tests, and the morphology at the failure opening of the specimens was similar to that observed in the result of post-irradiation examinations of high burnup fuel which failed during a pulse irradiation experiment. The longitudinal strain ($$varepsilon$$$$_{tz}$$) at failure clearly increased with increasing longitudinal tensile loads and the circumferential strain ($$varepsilon$$$$_{ttheta}$$) at failure significantly decreased in the case of 5.0 and 10.0 kN tests, compared with the case of 0 kN tests. It is considered that the data obtained in this study can be used as a fundamental basis for quantifying the failure criteria of fuel cladding under a biaxial stress state.

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パーセンタイル:75.69

分野:Nuclear Science & Technology

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