메뉴 건너뛰기




Volumn 123, Issue 2, 1996, Pages 305-316

Modeling water chemistry, electrochemical corrosion potential, and crack growth rate in the boiling water reactor heat transport circuits - III: Effect of reactor power level

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; ELECTROCHEMICAL CORROSION; HEAT PIPES; HYDROGEN; HYDROGEN PEROXIDE; OXYGEN; STAINLESS STEEL; STRESS CORROSION CRACKING; WATER;

EID: 0030169286     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE96-A24192     Document Type: Article
Times cited : (20)

References (16)
  • 7
    • 0003173094 scopus 로고
    • MS Thesis, Department of Nuclear Engineering, Massachusetts Institute of Technology
    • J. CHUN, "Modeling of BWR Water Chemistry," MS Thesis, Department of Nuclear Engineering, Massachusetts Institute of Technology (1990).
    • (1990) Modeling of BWR Water Chemistry
    • Chun, J.1
  • 8
    • 0029406351 scopus 로고
    • Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits - I: The DAMAGE-PREDICTOR Algorithm
    • T.-K. YEH, D. D. MACDONALD, and A. T. MOTTA, "Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits - I: The DAMAGE-PREDICTOR Algorithm," Nucl. Sci. Eng., 121, 468 (1995).
    • (1995) Nucl. Sci. Eng. , vol.121 , pp. 468
    • Yeh, T.-K.1    Macdonald, D.D.2    Motta, A.T.3
  • 9
    • 0030172104 scopus 로고    scopus 로고
    • Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits - II: Simulation of Operating Reactors
    • T.-K. YEH and D. D. MACDONALD, "Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits - II: Simulation of Operating Reactors," Nucl. Sci. Eng., 123, 295 (1996).
    • (1996) Nucl. Sci. Eng. , vol.123 , pp. 295
    • Yeh, T.-K.1    Macdonald, D.D.2
  • 10
    • 3643100884 scopus 로고
    • Cracking in the Lower Region of the Core Shroud in Boiling Water Reactors
    • U.S. Nuclear Regulatory Commission
    • "Cracking in the Lower Region of the Core Shroud in Boiling Water Reactors," NRC Information Notice 94-42, Suppl. 1, U.S. Nuclear Regulatory Commission (1994).
    • (1994) NRC Information Notice 94-42 , Issue.1 SUPPL.
  • 11
    • 84920632404 scopus 로고
    • Intergranular Stress Corrosion Cracking of Core Shroud in Boiling Water Reactors
    • U.S. Nuclear Regulatory Commission
    • "Intergranular Stress Corrosion Cracking of Core Shroud in Boiling Water Reactors," NRC Generic Letter 94-04, U.S. Nuclear Regulatory Commission (1994).
    • (1994) NRC Generic Letter 94-04
  • 15
    • 0003483748 scopus 로고
    • Corrosion-Assisted Cracking of Stainless and Low-Alloy Steels in LWR Environments
    • EPRI NP-5064M, Electric Power Research Institute Feb.
    • P. FORD et al., "Corrosion-Assisted Cracking of Stainless and Low-Alloy Steels in LWR Environments," Final Report, EPRI NP-5064M, Electric Power Research Institute (Feb. 1987).
    • (1987) Final Report
    • Ford, P.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.