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Extra resources for Analysis of PWR Critical Configurations Vol 4 - TMI Unit 1

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W. Hermann, and M. C. Brady, SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 2%Sequoyah Unit 2 Cycle 3, ORNL/TM-12294, Vol. , Oak Ridge Natl. , 1995. 26. S. M. Bowman and O. W. , Oak Ridge Natl. , 1995. 27. S. E. Turner, "An Uncertainty Analysis-Axial Burnup Distribution Effects," Proc. Workshop Use of Burnup Credit in Spent Fuel Transport Casks, Washington, DC, February 21-22, 1988, SAND89-0018, TTC-0884, UC-820, T. L. , Sandia Natl. , October 1989. 28. S. M. Bowman and M.

Table 8 gives the power history data used in the three fuel group models. Note that within each group model, a constant burn time per interval was used; this constant spacing is required by SNIKR when interpolating from SAS2H/ORIGEN output. To meet this requirement, the uptime for each of reactor operating cycles 2, 3, and 4 was assumed to be 300 days, representing the average cycle length. For groups 1 and 2, cycles 2 and 3 were divided into two intervals; for all groups, cycle 4 was divided into the number of intervals required so as to exceed the maximum assembly burnup by 20%.

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. of International Conference on Nuclear Criticality Safety, Christ Church, Oxford, United Kingdom, September 9-31, 1991. 5. O. W. Hermann and C. V. Parks, "SAS2H: A Coupled One-Dimensional Depletion and Shielding Analysis Code," Sect. S2 of SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, NUREG/CR-0200, Rev.

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Analysis of PWR Critical Configurations Vol 4 - TMI Unit 1


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