참고문헌
- Sandvik Steel Materials for the Nuclear Power Industry H. Widmark
- EPRI NP-2331 Sream Generator Corrosion Studies Cebelcor
- EPRI NP-3061 Stress Corrosion Cracking of 600 and Alloy 690 in All Volite Treated Water at Elevated Temperatures G.J. Theus
- EPRI NP-3043 Stress Corrosion of Alloy 600 and 690 in Acidic Sulfate Solutions at Elevated Temperatures J.F. Newman
- Fourth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors Relationship between Composition, Microstructure and Corrosion Behavior of Alloy 690 Steam Generator Tubing for PWR Systems A.Smith(et al.)
- Fifth International Symposium on Environmental Degradation of Materials in Niclear Power Systems-Water Reactors The Temperature Depedenance of Tensile Properties of Thermally Treated Alloy 690 Tubing D.L. Harrdo(et al.)
- Fifth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors Effectiveness of 700oC Thermally Treatment on Primary Water Stress Corrosion Sensitivity of 600 Steam Generator Tubes F. Cattant(et al.)
- EPRI NP-1354 Optimization of Metallurgical Variables to Improve the Stress Corrosion Resistance of Inconel 600 G.P. Airey
- KAERI/PR-765/88 Studies Related to the Secondary-Site SCC Evaluations in Steam Generator Tubes of Nuclear Power Plants W.C. Kim(et al.)
- KAERI/RR-1990/92 Study on Thermal & Mechanical Properties of U-Tube Material for Steam Generator W.S. Rhu
- Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors v.1 Experimental Residual Stress Evaluation of Hydraulic Expansion Transitions in Alloy 690 Steam Generator Tubing R. McGregor(et al.)
- EPRI NP-3055 Stress Relief to Prevent Stress Corrosion in the Transition Region of Expanded Alloy 600 Steam Generator Tubing J. Woodward(et al.)
- EPRI-NP5012 Stress Corrosion Cracking Test of Expanded Steam Generator Tubes G.V. Amoruso(et al.)
- ASTM Designation B163-86a Stradard Specification for Aeamless Nickel and Nickel Alloy Condenser and Heat Exchanger Tubes ASTM
- Journal of the Korean Nuclear Society v.29 no.2 Flare Test and Stress Analysis of Alloy 600/690 Tubes W.G. Kim;J. Jang;I.H. Kuk
- Mechanical Design Analysis M.F. Spotts
- Advanced Strength and Applied Elasticity(3rd Edition) A.C. Ugral(et al.)
- ASTM Designation B167-86 Standard Specifications for Nickel-Chromium-Iron Alloys (UNS N06600 and N06690) Seamless Pipe and Tube ASTM
- ASTM Designation E8-87a Standard Test Methods of Tension Testing of Metallic Materials ASTM
- Final Report, KAERI/RR-1764/96 Advanced Nuclear Material Development/Steam Generator Material I.H. Kuk(et al.)
- KAERI/CM-081/94 Characterization of Mechanical Properties of Inconel Alloys S.Y. Hong(et al.)
- Metal Forming: Mechanics and Metallurgy W. F. Hosford;R.M. Caddell