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Volumn , Issue 1354, 2000, Pages 505-524

Influence of composition and fabrication process on out-of-pile and in-pile properties of M5 alloy

Author keywords

[No Author keywords available]

Indexed keywords

ALLOYING ELEMENTS; CARBON; CORROSION; CREEP; CRYSTAL IMPURITIES; INGOTS; IRON; NIOBIUM; NUCLEAR FUEL CLADDING; OXYGEN; PRESSURIZED WATER REACTORS; SULFUR;

EID: 0033892352     PISSN: 10403094     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (173)

References (12)
  • 2
    • 0343254681 scopus 로고    scopus 로고
    • LWR Fuel Performance and Material Development Activities for Extended Burnup in Russia
    • 2-6 March
    • Solonin, M. I. et al., "LWR Fuel Performance and Material Development Activities for Extended Burnup in Russia," ANS Portland, 2-6 March 1997.
    • (1997) ANS Portland
    • Solonin, M.I.1
  • 4
    • 0343690354 scopus 로고
    • A Metallographic Study of Annealing of Zr-1 Nb Nuclear Fuel Sheathing
    • Derek, A. D. and Northwood, G. A, "A Metallographic Study of Annealing of Zr-1 Nb Nuclear Fuel Sheathing," Microstructural Science, Vol. 17, 1989, p. 393.
    • (1989) Microstructural Science , vol.17 , pp. 393
    • Derek, A.D.1    Northwood, G.A.2
  • 5
    • 0030291013 scopus 로고    scopus 로고
    • Influence of Neutron Irradiation on Dislocation Structure and Phase Composition of Zr-Base Alloys
    • Shishov, V. N. et al., "Influence of Neutron Irradiation on Dislocation Structure and Phase Composition of Zr-Base Alloys," Zirconium in the Nuclear Industry (11th Volume), ASTM STP 1295, pp. 603-622.
    • Zirconium in the Nuclear Industry (11th Volume), ASTM STP 1295 , pp. 603-622
    • Shishov, V.N.1
  • 6
    • 0343254679 scopus 로고    scopus 로고
    • Update on the Development of Advanced Zirconium Alloys for PWR Fuel Rod Cladding
    • 2-6 March
    • Mardon, J. P. et al., "Update on the Development of Advanced Zirconium Alloys for PWR Fuel Rod Cladding," ANS Portland, 2-6 March 1997, pp. 405-413.
    • (1997) ANS Portland , pp. 405-413
    • Mardon, J.P.1
  • 7
    • 0342820010 scopus 로고
    • Influence des Traitements Thermiques sur les Propriétés des Tubes de Gainage en Alliages Zirconium-Niobium (1 et 2.5%Nb)-Etude Particulière du Comportement en Fluage Thermique Biaxé
    • 15 Dec.
    • Golhen, J. F., "Influence des Traitements Thermiques sur les Propriétés des Tubes de Gainage en Alliages Zirconium-Niobium (1 et 2.5%Nb)-Etude Particulière du Comportement en Fluage Thermique Biaxé," Thèse CNAM Paris, 15 Dec. 1993, pp. 54-57.
    • (1993) Thèse CNAM Paris , pp. 54-57
    • Golhen, J.F.1
  • 9
    • 0343690357 scopus 로고    scopus 로고
    • "French Patent," FR 2747397, 16 April 1996
    • Rebeyrolle, V., "French Patent," FR 2747397, 16 April 1996.
    • Rebeyrolle, V.1
  • 11
    • 0032074007 scopus 로고    scopus 로고
    • Influence of Sulfur Content on the Thermal Creep of Zirconium Alloy Tubes at 400°C
    • Charquet, D., "Influence of Sulfur Content on the Thermal Creep of Zirconium Alloy Tubes at 400°C," Journal of Nuclear Materials, Vol. 255, 1998, pp. 78-82.
    • (1998) Journal of Nuclear Materials , vol.255 , pp. 78-82
    • Charquet, D.1
  • 12
    • 0040109968 scopus 로고    scopus 로고
    • Optimization of PWR Behavior of Stress-Relieved Zircaloy-4 Cladding Tubes by Upgrading the Manufacturing and Inspection Process
    • Mardon, J. P., Charquet, D., and Senevat, J., "Optimization of PWR Behavior of Stress-Relieved Zircaloy-4 Cladding Tubes by Upgrading the Manufacturing and Inspection Process," Zirconium in the Nuclear Industry (10th Vol.), ASTM STP 1245, pp. 329-348.
    • Zirconium in the Nuclear Industry (10th Vol.), ASTM STP 1245 , pp. 329-348
    • Mardon, J.P.1    Charquet, D.2    Senevat, J.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.