The Effect of Final Heat Treatment and Welding on Irradiation Growth of Zircaloy-4

최종열처리와 용접Zircaloy-4의 방사선조사 성장에 미치는 영향

  • Published : 1993.02.01

Abstract

Abstract The effect of final heat treatment and welding on the irradiation growth of Zircaloy-4 was investigated. As a simulation for neurtron irradiation, accelerated proton beam with the energy of 3.5MeV was used up to the proton fluence of 9.8 ${\times}{10^{21}}$p/$m^2$ in the present study. It was found that irradiation growth of the annealed specimen was the highest and that of the ${\beta}$-quenched specimen was the samllest among the present specimens. The magnitude of irradiation growth of the present specimens decreased by welding. The difference in the magnitude of irradiation growth of the present specimens with different final heat treatment and the effect of welding on it were quantitatively analyzed in terms of crystallographic texture by using Kearns number, f, which was calculated from the x-ray diffraction data.

최종열처리와 용접이Zircaloy-4의 방사선조사 성장에 미치는 영향을 조사하였다. 본 연구에서는 중성자 조사에 대한 모의시험으로 3.5MeV로 가속된 양심자 빔을 조사량 9.8 ${\times}{10^{21}}$p/$m^2$까지 시편에 조사하였다. 본 연구에 사용된 시편중znnealed 시편의 방사선조사성장이 가장 컸으며 ${\beta}$-quenched 시편의 방사선조사 성장이 제일 작았다. 방사선조사 성장의 크기는 용접을 함에 따라 감소하였다. 최종열처리 조건의 차이에 의한 방사선조사 성장크기에서의 차이와 용접이 방사선조사 성장에 미치는 영향을 ray 회절시험으로부터 계산된 Kearns number, f,를 이용하여 정량적으로 분석하였다.

Keywords

References

  1. Atomic Energy Rev. v.13 V.Fidleris
  2. Can. Metal. Q. v.18 R.G.Fleck
  3. J. Nucl. Mater. v.91 E.F.Ibrahim(et al)
  4. ASTM STP 824 R.G.Fleck(et al.)
  5. ASTM Zirconium Conference High Temperature Irradiation Growth in Zircaloy R.B.Adamson(et al)
  6. Properties of Reactor Materials and the Effects of Irradiation Damage S.N.Buckley
  7. Nucl Tech. v.14 R.C.Daniel
  8. ASTM STP 633 R.B.Adamson
  9. Radiation Damage in Reactor Materials 1 R.V.Hesketh(et al)
  10. J. Nucl. Mater. v.45 E.F.Ibrahim;J.E.Winegar
  11. ASTM STP 484 J.E.Harbottle
  12. Properties of Materials for Water Reactor Fuel Elements and Methods of Measurements F.Garzarolli(et al)
  13. Can. Met. Quart. v.11 K.Kallstrom
  14. ASTM STP 551 K.Kallstrom;T.Anderson;A.Hofvenstram
  15. J. Nucl. Mater. v.77 B.D.Knorr;R.M.Pelloux
  16. Westinghouse Co. Report WAPD-TM-472 J.J.Kearns
  17. ASTM STP 611 D.G.Doran(et al)
  18. ORNL-4897 O.S.Oen
  19. J. Nucl. Mater. v.82 R.A.Holt
  20. Radiation Damage in Reactor Materials Vol 1 R.V.Hesketh;J.E.Harbottle;N.A.Waterman;R.C.Lobb
  21. J. Nucl. Mater. v.80 A.Rogerson;R.A.Murgatroyd
  22. Private Communication with Dr. Weidinger at KWU