TY - JOUR
T1 - Development of advanced expansion due to compression (A-EDC) test method for safety evaluation of degraded nuclear fuel cladding materials
AU - Abe, Hiroaki
AU - Abe, Tomonori
AU - Kishita, Shiori
AU - Kano, Sho
AU - Li, Yanfen
AU - Yang, Huilong
AU - Tawara, Kyosuke
AU - Matsukawa, Yoshitaka
AU - Satoh, Yuhki
N1 - Publisher Copyright:
© 2015 Atomic Energy Society of Japan. All rights reserved.
PY - 2015/10/3
Y1 - 2015/10/3
N2 - Expansion due to compression (EDC) test has been applied to evaluate the performance of nuclear fuel claddings where pellet-cladding mechanical interaction (PCMI) is introduced by swelling of fuel pellets and is triggered by the larger hoop deformation of the pellets, especially during accidental transients. The purpose of this study is to modify the EDC test to describe PCMI, specimen volume reduction and others. Ring-shaped specimens were cut from Zry-4 cladding tubes. Cylindrical metal pellets with 8 mm in diameter and 15 mm in maximum height were used as inner pellets. Expansion of the specimens due to the inner pellet compression was performed at room temperature. The experimental data were further analyzed by finite element method. Through the survey in the variation of the specimen and core, specimen size and inner pellet geometry were optimized. Excellent reproducibility with less error was confirmed. The uniaxial tension condition in the hoop direction up to the specimen failure was confirmed. Hoop stress-hoop strain curves were successfully derived.
AB - Expansion due to compression (EDC) test has been applied to evaluate the performance of nuclear fuel claddings where pellet-cladding mechanical interaction (PCMI) is introduced by swelling of fuel pellets and is triggered by the larger hoop deformation of the pellets, especially during accidental transients. The purpose of this study is to modify the EDC test to describe PCMI, specimen volume reduction and others. Ring-shaped specimens were cut from Zry-4 cladding tubes. Cylindrical metal pellets with 8 mm in diameter and 15 mm in maximum height were used as inner pellets. Expansion of the specimens due to the inner pellet compression was performed at room temperature. The experimental data were further analyzed by finite element method. Through the survey in the variation of the specimen and core, specimen size and inner pellet geometry were optimized. Excellent reproducibility with less error was confirmed. The uniaxial tension condition in the hoop direction up to the specimen failure was confirmed. Hoop stress-hoop strain curves were successfully derived.
KW - cladding
KW - expansion due to compression test (EDC test)
KW - mechanical property
KW - pellet-cladding mechanical interaction (PCMI)
KW - ring test
KW - zirconium alloy
UR - http://www.scopus.com/inward/record.url?scp=84939466487&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=84939466487&partnerID=8YFLogxK
U2 - 10.1080/00223131.2015.1056560
DO - 10.1080/00223131.2015.1056560
M3 - Article
AN - SCOPUS:84939466487
VL - 52
SP - 1232
EP - 1239
JO - Journal of Nuclear Science and Technology
JF - Journal of Nuclear Science and Technology
SN - 0022-3131
IS - 10
ER -