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Volumn 1295, Issue , 1996, Pages 850-864

Comparison of the long-time corrosion behavior of certain Zr alloys in PWR, BWR, and laboratory tests

Author keywords

Corrosion; In BWR corrosion; In PWR corrosion; Neutron irradiation; Nuclear application; Out of pile corrosion; Radiation effects; Zircaloy; Zirconium alloys

Indexed keywords

BOILING WATER REACTORS; COMPOSITION EFFECTS; CORROSION RESISTANCE; PRESSURIZED WATER REACTORS; RADIATION EFFECTS;

EID: 0030285165     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/stp16204s     Document Type: Review
Times cited : (38)

References (10)
  • 5
    • 0342385212 scopus 로고
    • Cladding and Structural Material Development for the Advanced Siemens PWR Fuel FOCUS
    • Proceedings, Avignon, France
    • Fuchs, H. P. et al., "Cladding and Structural Material Development for the Advanced Siemens PWR Fuel FOCUS," Proceedings, ANS-ENS Internal Topical Meeting on LWR Fuel Performance, Avignon, France, 1991, p. 682.
    • (1991) ANS-ENS Internal Topical Meeting on LWR Fuel Performance , pp. 682
    • Fuchs, H.P.1
  • 8
    • 0343254731 scopus 로고
    • Corrosion Performance of Some Zirconium Alloys Irradiated in the Steam Generating Heavy Water Reactor Winfrith
    • Proceedings, Myrtle Beach, SC, NACE
    • Cheng, B. et al.. "Corrosion Performance of Some Zirconium Alloys Irradiated in the Steam Generating Heavy Water Reactor Winfrith," Proceedings, International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Myrtle Beach, SC, 1983, NACE, p 274
    • (1983) International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , pp. 274
    • Cheng, B.1
  • 9
    • 5544326592 scopus 로고
    • In BWR and Out-of-Pile Nodular Corrosion Behavior of Zry 2/4 Type Melts with Varying Fe, Cr, and Ni Contents and Varying Process History
    • Proceedings, 11-14 Sept.
    • Ruhman, H., Manzel, R., and Charquet, D., "In BWR and Out-of-Pile Nodular Corrosion Behavior of Zry 2/4 Type Melts with Varying Fe, Cr, and Ni Contents and Varying Process History," Proceedings Eleventh ASTM Symposium on Zirconium in the Nuclear Industry, 11-14 Sept. 1995.
    • (1995) Eleventh ASTM Symposium on Zirconium in the Nuclear Industry
    • Ruhman, H.1    Manzel, R.2    Charquet, D.3
  • 10
    • 0342820027 scopus 로고
    • Optimized Zry-4 with Enhanced Fe and Cr Content and DUPLEX Cladding: The Answer to Corrosion on PWR
    • Proceedings, TOPFUEL 95, Würzburg, Germany, 12-15 March
    • Seibold, A., Garzarolli, F., and Steinberg, E., "Optimized Zry-4 with Enhanced Fe and Cr Content and DUPLEX Cladding: the Answer to Corrosion on PWR," Proceedings, International KTG/ENS Topical Meeting on Nuclear Fuel, TOPFUEL 95, Würzburg, Germany, 12-15 March 1995, Vol. II, p. 117.
    • (1995) International KTG/ENS Topical Meeting on Nuclear Fuel , vol.2 , pp. 117
    • Seibold, A.1    Garzarolli, F.2    Steinberg, E.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.