Analysis of PWR Critical Configurations Vol 4 - TMI Unit 1

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1, 2 and 3 (draft November 1993). Available from Radiation Shielding Information Center as CCC-545. 17. T. A. Coleman and P. B. McCanna, Core Operation Report (End of Cycle 1) Three Mile Island Unit 1, Cycle 1 Operation September 2, 1974 - February 21, 1976, BAW-1443, Babcock and Wilcox, October 22, 1976. 38 18. T. A. Coleman and P. B. McCanna, Core Operation Report: Three Mile Island Unit 1, Cycle 2 Operation May 24, 1976 - March 18, 1977, BAW-1459, Babcock and Wilcox, April 1976. 19. W. Bojduj, Core Operation Report: Three Mile Island Unit 1, Cycle 3 Operation May 13, 1977 - March 17, 1978, BAW-1503, Babcock and Wilcox, August 1976.

A mixture number (102), and the 23 Table 9. Fuel assembly data for one-eighth core geometry Assembly No. 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 Assembly type Fuel group 4B 5 6 4B 6 5 6 7 6 5 6 5 6 4B 7 6 5 6 4B 7 7 5 5 6 7 4B 7 7 5 1 2 3 1 3 2 3 4 3 2 3 2 3 1 4 3 2 4 1 4 4 2 2 3 4 1 4 4 2 Average burnup Subgroup (MWd/MTU) 1 4 8 1 6 4 6 9 7 3 8 4 7 1 9 7 5 8 1 9 9 4 5 6 9 2 9 9 5 25,199 18,313 6,683 23,926 9,540 17,603 9,540 0 7,969 20,929 5,802 18,740 7,090 24,728 0 7,969 16,615 6,012 24,900 0 0 18,203 15,877 9,322 0 21,034 0 0 15,838 24 cross-section ID modifier (4) are specified (fuel materials in assemblies 1 through 29 were assigned mixture numbers 101 through 129, respectively).

L. Sanders and R. M. Westfall, "Feasibility and Incentives for Burnup Credit in Spent Fuel Transport Casks," Nucl. Sci. Eng. 104 (1990). 2. 1-1983. 3. SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, NUREG/CR-0200, Rev. 4 (ORNL/NUREG/CSD-2/R4), Vols. I, II, and III (draft November 1993). Available from Radiation Shielding Information Center as CCC-545. 4. M. C. Brady and T. L. Sanders, "A Validated Methodology for Evaluating Burnup Credit in Spent Fuel Casks," Proc.

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