참고문헌
- ASTM STP 1132 Zirconium-Alloy Corrosion: A Review Based on an International Atomic Energy Agency (IAEA) Meeting D.G. Franklin;P.M. Lang
- KINS, KINS/AR-107 Periocdic Inspection Report of Wolsong Unit 1(1992) W.G. Shin
- COG/IAEA 4th PHWR Conference Monitoring Pressure Tube Health by Micro-sampling P. Janzen;R. Joynes;L. W. Green;V. Urbanic
- Institute of Inorganic Materials, VNIINM v.2 no.36 Process of RBMK Pressure Tube Fabrication from Zr-2.5% Nb Alloy A. V. Nikulina;N.G. Reshetnikov;P.V. Schebaldov
- KINS, KINS/AR-107 v.4 Periodic Inspection Report of Wolsong Unit 1(1994) W. G. Shin
- AECL Report 59-31100-220-032 A Blister Assesment of Selected Fuel Channels in Wolsong 1 G.D. Moan
- ASTM STP 1023 Oxidation and Deuterium Uptake of Zr-2.5Nb Pressure Tubes in CANDU-PHW Reactors V.F. Urbanic;B.D. Warr;A. Manolescu;C.K. Chow;M.W. Sahan
- Revs. of Coatings and Corrosion v.3 Delayed hydrogen cracking in Zr-2.5 wt% Nb Alloys C. E. Coleman;J.F.R. Ambler;J. YAHALOM(Ed.)
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J. Nucl. Mater
v.226
Oxiation and hydrogen uptake of Zr based alloys at 400℃ under 10MPa
$H_2O$ steam atmosphere K.N. Choo;S.I.Pyun;Y.S. Kim - CAN/CSA-N285.4-M94 Periodic Inspection of CANDU Nuclear Power Plant Components A National Standard of Canada
- J. Testing Eval. v.17 Influence of Heat Treatment on Structure and Oxidation Behavior of Zr 2.5Nb L. V. Ramanathan;I. Costa;ana W.A. Monteiro
- ASTM STP 1132 Enhancement of Aqueous Corrosion of Zircaloy-4 Due to Hydride Precipitation at the Metal-Oxide Interface A.M. Garde
- J. Nucl. Mater. v.209 Effect of Composition and Heat Treatment on the Microstructure and Corrosion Behavior of Zr-Nb Alloys K.N. Choo;Y.H. Kang;S.I. Pyun;V.F. Urbanic
- J. Nucl. Mater. v.22 Terminal Solid Solubility and Partitioning of Hydrogen in the Alpha Phases of Zirconium, Zircaloy-2 and Zircaloy-4 J.J. Kearns
- ASTM STP 1132 Electron Microscopical Analyses of Oxides in Zr-2.5 wt% Nb B.D. Warr;E.M. Rasile;M.B. Elmoselhi
- J. Nucl. Mater. v.9 no.1 Zr-Nb Binary Alloys for BWR Service H.H. Klepfer