링 인장시험을 이용한 지르코늄 피복관의 반응도 사고(RIA) 시 연성 평가

김준환; 이명호; 최병권; 방제건; 정용환; Jun Hwan Kim; Myoung Ho Lee; Byoung Kwon Choi; Je Geon Bang; Yong Hwan Jeong

Korean Journal of Materials Research, Vol.15, No.2, 126-133, February, 2005

DOI10.3740/MRSK.2005.15.2.126 Export Citation

링 인장시험을 이용한 지르코늄 피복관의 반응도 사고(RIA) 시 연성 평가

Evaluation of Ductility During Reactivity Initiated Accident for Zirconium Cladding using Ring Tension Test

김준환^†, 이명호, 최병권, 방제건, 정용환

한국원자력연구소

Jun Hwan Kim^†, Myoung Ho Lee, Byoung Kwon Choi, Je Geon Bang, and Yong Hwan Jeong

Zirconium Fuel Cladding Development Team, Korea Atomic Energy Research Institute, Daejeon 305-353, Korea

E-mail:

Mechanical properties of zirconium cladding were evaluated by ring tension test to simulate Reactivity-Initiated Accident (RIA) at high burnup situation as an out-reactor test. Zircaloy-4 cladding was hydrided up to 1000 ppm as well as oxidized up to 100μm to simulate high-burnup situation. After simulated high-burnup treatment, ring tension test was carried out from 0.01 to 1/sec to correlate with actual RIA event. The results showed that ductility and circumferential toughness decreased with the hydrogen content and oxide thickness. Hydride generated inside cladding acted as brittle failure. Oxygen influenced cladding tube by the reduction of load bearing area, oxygen embrittlement, and thermal aging. Correlation between in-reactor RIA parameter like fuel enthalpy and out-reactor toughness was performed and showed a reasonable result.

Keywords:reactivity initiated accident (RIA);ring tension test;hydride;oxide;fuel enthalpy

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[Related Articles]

[1] Montgomery R, Waeckel N, Yang R, 29th Annual NRC Water Reactor Safety Meeting, 22-24 Oct., Washington, U.S.A., 409 (2001) (2001)

[2] MacDonald PE, Seiffer SL, Martinson ZR, McCardell RK, Owen DE, Fukuda SK, Nuclear Safety, 21, 582 (1980)

[3] Yvon P, Catherine CS, Duguay C, Carassou S, Hourdequin N, Cazalis B, Bemaudat C, IAEA Technical Meeting on Fuel Behavior under Transient and LOCA conditions, 10-14 Sept., Halden, Norway (2001) (2001)

[4] Nagase F, Otomo T, Uetsuka H, JAERI-Research 98064 (1998) (1998)

[5] Cohen AB, Majumdar S, Ruther WE, Billone MC, Chung HM, Neimark LA, 25th Annual NRC Water Reactor Safety Meeting, 20-22 Oct., Bethesda, U.S.A, 133 (1997) (1997)

[6] Yegorova L, Lioutov K, Kaplar E, 29th Annual NRC Water Reactor Safety Meeting, 22-24 Oct., Washington, U.S.A., 343 (2001) (2001)

[7] Lee MH, Kim JH, Choi BK, Jeong YH, Korean J. Mater. Res., 14(10), 713 (2004)

[8] Kim JH, Lee JH, Choi BK, Jeong YH, J. Kor. Inst. Met. Mater., 42, 656 (2004)

[9] MATPRO - Version 11, NUREG CR-0497 (1979) (1979)

[10] Schmitz F, Papin J, 26th Annual NRC Water Reactor Safety Meeting, 26-28 Oct., Bethesda, U.S.A, 243 (1998) (1998)

[11] Fuketa F, Nagase F, Ishijima K, Fukishiro T, Nuclear Safety, 37, 328 (1996)