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Extra resources for Research Reactor Core Conversion Guidebook Vol 3 [Analytical Verification] (IAEA TECDOC-643v3)
H. Henryson II, B. J. Toppel and C. G. Stenberg, "MC^-2: A Code to Calculate Fast Neutron Spectra and Multigroup Cross Sections", ANL-8144 (ENDF239) (June, 1976) 4. T. A. Daley, G. K. Leaf and A. S. Kennedy, "The ARC System Two-Dimensional Diffusion Theory Capability, DARC2D, "ANL-7716 (May, 1972). 5. R. E. Prael and L. J. Milton, "A User's Manual for the Monte Carlo Code VIM,' FRA-TM-84 (February 20, 1976). 6. C. F. Obenchain, "PARET - A Program for the Analysis of Reactor Transients," IDO-17282 (1969).
5%. For convenience of potential users, micropscopic absorption cross sections for the materials in the Ag-In-Cd, B^C, and Hf control blades obtained from the Monte Carlo calculations are shown in Tables 16, 17, and 18. In addition, the Monte Carlo values of the parameter a = ^Itr that were used in the diffusion theory calculations are shown in Table 19 for all three types of absorber blades in the fresh HEU and LEU cores. There are only small differences between the values of "a" in the HEU and LEU cores.
18. Although this core did not include destructive tests, the HEU benchmark core limiting case is included for comparison purposes. An extrapolation of the data for the B-24/32 core would suggest that the benchmark core would also agree well with this SPERT I data. 75 s). The areas above the curves indicate where clad melting would be expected. Also shown in this figure is the corresponding maximum net reactivity inserted (the difference between the external reactivity inserted and the reactivity from feedback).