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Volumn 37, Issue 5, 2000, Pages 455-464

Behavior of irradiated ATR/MOX fuel under reactivity initiated accident conditions

Author keywords

ATR MOX fuel; Cladding deformation; Fission gas release; NSRR; PCMI; Pellet swelling; Plutonium spots; Pulse irradiation; Reactivity initiated accident

Indexed keywords

CRACK INITIATION; DEFORMATION; ENTHALPY; FISSION PRODUCTS; IRRADIATION; MICROCRACKS; NUCLEAR FUEL CLADDING; NUCLEAR FUEL PELLETS; NUCLEAR REACTOR ACCIDENTS; RADIATION EFFECTS; REACTIVITY (NUCLEAR); SWELLING;

EID: 0033726444     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2000.9714918     Document Type: Article
Times cited : (14)

References (16)
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  • 5
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  • 9
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    • MATPRO-Version 11: A handbook of materials properties for use in the analysis of light water reactor fuel rod behavior
    • Hagrman, D. L., Gregory A. R.: MATPRO-Version 11: A handbook of materials properties for use in the analysis of light water reactor fuel rod behavior, NUREG/CR-Om, TREE-1280, R3, (1979).
    • (1979) Nureg/Cr-Om, TREE-1280 , pp. R3
    • Hagrman, D.L.1    Gregory, A.R.2
  • 12
    • 85010505208 scopus 로고    scopus 로고
    • Behavior of irradiated ATR/MOX fuel under reactivity initiated accident conditions
    • [in Japanese]
    • Sasajima, H., et al: Behavior of irradiated ATR/MOX fuel under reactivity initiated accident conditions, JAERI-Research 99-060, (1999), [in Japanese].
    • (1999) Jaeri-Research , pp. 99-60
    • Sasajima, H.1
  • 13
    • 78751665808 scopus 로고    scopus 로고
    • New results from the NSRR experiments with high burnup fuel
    • Bethesda, U.S.A., Oct
    • Fuketa, T., et al: New results from the NSRR experiments with high burnup fuel, Proc. 23rd Water Reactor Safety Information Meeting, Bethesda, U.S.A., Oct. 23, 1995, (1996).
    • (1996) Proc. 23Rd Water Reactor Safety Information Meeting , vol.23 , pp. 1995
    • Fuketa, T.1
  • 14
    • 0040703677 scopus 로고
    • Behavior of irradiated PWR fuel under a simulated RIA condition; Results of NSRR test MH-3
    • Sasajima, H., et al: Behavior of irradiated PWR fuel under a simulated RIA condition; Results of NSRR test MH-3, JAERI-Research 95-087, (1995).
    • (1995) Jaeri-Research , pp. 95-87
    • Sasajima, H.1
  • 16
    • 85010615761 scopus 로고    scopus 로고
    • Operation experiences in MOX fuel fabrication for advanced thermal reactor, “Fugen”
    • Experience, Advances, Trends., Vienna, Austria, May 17-21
    • Okita, T., et al: Operation experiences in MOX fuel fabrication for advanced thermal reactor, “Fugen”, Int. Symp. on MOX Fuel Technologies for Medium and Long Term Deployment; Experience, Advances, Trends., Vienna, Austria, May 17-21, 1999.
    • (1999) Int. Symp. on MOX Fuel Technologies for Medium and Long Term Deployment
    • Okita, T.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.