Analysis of PWR Critical Configurations Vol 1 - Summary

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It is neither desired nor desirable to base spent fuel calculations on the unique operating history of each fuel pin in each assembly in a core. Hence, it is necessary to make assumptions as to what approximations are suitable in representing the composition of a spent fuel assembly from a reactor core. The methodology described in Sect. 2 of this report provides a procedure for approximating the composition of a core; additional details related to the specific designs included in this report are given in Sect.

D. Murphy L. F. Norris J. V. Pace 24-28. 29. 30. 31. 32. 33. 34. 35. 36. 37. 38. 39-40. 41. 42. 43. 44. C. V. Parks L. M. Petrie R. T. -P. Renier J. W. Roddy R. W. Roussin J. C. Ryman C. H. Shappert R. M. Westfall B. A. Worley R. Q. Wright Laboratory Records Dept. Laboratory Records, ORNL-RC Document Reference Section ORNL Y-12 Research Library Central Research Library ORNL Patent Section EXTERNAL DISTRIBUTION 45. R. , Columbia, SC 29210 46. M. G. S. Nuclear Regulatory Commission, MS TWFN 8F5, Washington, DC 20555 47.

O. Box 85608, 10955 John J. , San Diego, CA 92121 53. M. C. Brady, Sandia National Laboratories, 101 Convention Center Drive, Suite 880, Las Vegas, NV 89109 54. P. S. Department of Energy, RW-1, Washington, DC 20545 55. R. J. , Framington, MA 01701 56. R. O. Box 808, Livermore, CA 94550 57. C. R. S. Nuclear Regulatory Commission, Office of Nuclear Materials Safety and Safeguards, TWFN 8F5, Washington, DC 20555 58. J. S. O. Box 808, Livermore, CA 94550 59. J. Clark, 2650 Park Tower Drive, Suite 800, Vienna, VA 22180 33 34 60.

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