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Volumn 1, Issue , 2001, Pages 201-205

Interim dry storage of PWR spent fuel assemblies - Development of a long term creep law to assess the fuel cladding integrity

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; CREEP TESTING; DATABASE SYSTEMS; EQUATIONS OF STATE; FUEL STORAGE; IRRADIATION; LOADS (FORCES); NUCLEAR FUEL CLADDING; NUCLEAR FUEL REPROCESSING; PRESSURE EFFECTS; RECYCLING; SAFETY FACTOR;

EID: 0346961335     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (11)

References (11)
  • 2
    • 0347978804 scopus 로고    scopus 로고
    • Anisotropy viscoplastic behavior of Zircaloy 4 cladding tubes under simulated load follow conditions
    • Portland, Oregon. March
    • P.BOUFFIOUX, P.GEYER: "Anisotropy viscoplastic behavior of Zircaloy 4 cladding tubes under simulated load follow conditions". ANS International Topical Meeting on LWR Fuel Performance, Portland, Oregon. March 1997.
    • (1997) ANS International Topical Meeting on LWR Fuel Performance
    • Bouffioux, P.1    Geyer, P.2
  • 3
    • 0033881232 scopus 로고    scopus 로고
    • Impact of hydrogen on plasticity and creep of unirradiated Zircaloy 4 cladding tubes
    • January
    • P.BOUFFIOUX, N.RUPA: "Impact of hydrogen on plasticity and creep of unirradiated Zircaloy 4 cladding tubes". ASTM STP 1354, pp 399-420, January 2000.
    • (2000) ASTM STP , vol.1354 , pp. 399-420
    • Bouffioux, P.1    Rupa, N.2
  • 5
    • 0346718048 scopus 로고    scopus 로고
    • Creep and relaxation behavior of unirradiated and irradiated stress-relieved cladding tubes
    • A.SONIAK and co: "Creep and relaxation behavior of unirradiated and irradiated stress-relieved cladding tubes". ASTM STP 1325, 1997.
    • (1997) ASTM STP , vol.1325
    • Soniak, A.1
  • 6
    • 0347978824 scopus 로고
    • Comportement á la corrosion de matériaux de gainage en Zircaloy 4 pour de forts taux de combustion dans les REP d'EDF
    • septembre
    • M.BLAT and co: "Comportement á la corrosion de matériaux de gainage en Zircaloy 4 pour de forts taux de combustion dans les REP d'EDF". Colloque international FONTEVRAUD III, septembre 1994.
    • (1994) Colloque International FONTEVRAUD III
    • Blat, M.1
  • 7
    • 0025429818 scopus 로고
    • Creep deformation of an unirradiated Zircaloy nuclear fuel cladding tube under dry storage conditions
    • M.MAYUZUMI, T.ONCHI: "Creep deformation of an unirradiated Zircaloy nuclear fuel cladding tube under dry storage conditions". Journal of Nuclear Materials, volume 171, pp 381-388, 1990.
    • (1990) Journal of Nuclear Materials , vol.171 , pp. 381-388
    • Mayuzumi, M.1    Onchi, T.2
  • 8
    • 0019265668 scopus 로고
    • The generation of reliable design data for long term high temperature creep applications
    • ICM 3, Pergamon Press
    • M.R.WARREN: "The generation of reliable design data for long term high temperature creep applications". Mechanical Behaviour of Materials, ICM 3, volume 2, Pergamon Press, 1980.
    • (1980) Mechanical Behaviour of Materials , vol.2
    • Warren, M.R.1
  • 11
    • 0347978825 scopus 로고    scopus 로고
    • Effect of hydriding on the residual cold work recovery and creep of zircaloy 4 cladding tubes
    • Park City, Utah. April
    • P. BOUFFIOUX, L. LEGRAS: "Effect of hydriding on the residual cold work recovery and creep of zircaloy 4 cladding tubes". ANS International Topical Meeting on LWR Fuel Performance, Park City, Utah. April 2000.
    • (2000) ANS International Topical Meeting on LWR Fuel Performance
    • Bouffioux, P.1    Legras, L.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.