Hydrogen Absorption Behavior of Zr-2.5Nb Pressure Tubes in Wolsong Unit 1

  • 발행 : 1998.08.01

초록

The deuterium uptake behavior of Zr-2.5Nb pressure tubes in Wolsong Unit 1 was analyzed in terms of longitudinal location, operation time, and coolant temperature. The results were compared with those obtained from Canadian CANDU reactors. The amount of deuterium uptake was higher at the outlet part than at the inlet part and was also higher when subjected to a longer operation time and a higher coolant temperature. The hydrogen uptake of Zr-2.5Nb in a hydrogen gas atmosphere was dependent on the microstructure of the alloy. The aged Zr-2.5Nb consisting of $\alpha$-Zr and $\beta$-Nb phases showed higher hydrogen uptake than that consisting of $\alpha$-Zr and $\beta$-Zr phases. The hydrogen in the alloy decreased the rate of oxidation. This could be explained in terms of the cathodic controlled reaction of Zr-2.5Nb oxidation.

키워드

참고문헌

  1. ASTM STP 1132 Zirconium-Alloy Corrosion: A Review Based on an International Atomic Energy Agency (IAEA) Meeting D.G. Franklin;P.M. Lang
  2. KINS, KINS/AR-107 Periocdic Inspection Report of Wolsong Unit 1(1992) W.G. Shin
  3. COG/IAEA 4th PHWR Conference Monitoring Pressure Tube Health by Micro-sampling P. Janzen;R. Joynes;L. W. Green;V. Urbanic
  4. 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
  5. KINS, KINS/AR-107 v.4 Periodic Inspection Report of Wolsong Unit 1(1994) W. G. Shin
  6. AECL Report 59-31100-220-032 A Blister Assesment of Selected Fuel Channels in Wolsong 1 G.D. Moan
  7. 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
  8. 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.)
  9. 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
  10. CAN/CSA-N285.4-M94 Periodic Inspection of CANDU Nuclear Power Plant Components A National Standard of Canada
  11. 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
  12. ASTM STP 1132 Enhancement of Aqueous Corrosion of Zircaloy-4 Due to Hydride Precipitation at the Metal-Oxide Interface A.M. Garde
  13. 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
  14. 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
  15. ASTM STP 1132 Electron Microscopical Analyses of Oxides in Zr-2.5 wt% Nb B.D. Warr;E.M. Rasile;M.B. Elmoselhi
  16. J. Nucl. Mater. v.9 no.1 Zr-Nb Binary Alloys for BWR Service H.H. Klepfer