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For a particular fusion-reactor-blanket configuration, the changes in the tritium breeding ratio, i.e., in the number of tritium nuclei produced in the blanket per incident neutron, due to changes in nuclear cross-section data are calculated on the basis of linear perturbation theory. Results are presented for the changes in the breeding ratio due to changes i n specific energy ranges of various partial cross sections of 6~i , 7~i , Nb, and C. The breeding ratio is found to be most sensitive to changes in the 7~i(n,n1)a,t cross section, but the sensitivity to changes in this cross section is not large. * * * zero. In terms of 6C, the quantity [HU-Hp] mu, which occurs i n Eq. 9, may be m i t t e n ' r L i 6~i L (n,2n1)a,p B. 9

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This report describes e preliminary comparative evaluation of pebble bed and pris matic fuel configurations for high-temperature gas-cooled reactor cores and was prepared fcr the Gas Cooled Reactor Programs Division (G. A. Newby, Acting Director), U.S. Depart ment of Energy. Reactor outlet coolant temperatures of 730, 850. and S50°C and reactor siies of 3000 and 1000 MW(t) were considered. The basic studies were carried out over a period of about six months and involved specific relative evaluations, as well as a review of the general information that was available Because of the time limitations, fie evaluations were largely carried out utilizing reference designs in comparing the two reactor concepts. Although not evident on r.he basis of the understanding developed during this study, design reoptimization relative to some of the specific parameters considered to be important here might influence the comparative results; such reoptimizations were not carried out here. The evaluation results given here are those determined by Oak Ridge National Laboratory; however, we wish to acknowledge the significant contributions made by other participants in providing information useful to this study. In particular, we wish to acknowledge the assistance of (1) General Atomic Company (E. 0. Winkler, coordinator) in the areas of design, thermal hydraulics, fission-product behavior, safety studies, fuel cycle performance, maintenance requirements, and fuel reprocessing technology and costs; (2) General Electric Company (G. R. Pflasterer, coordinator) in the areas of reactor avail-aDility, control and design; (3) Gas-Cooled Reactor Associates (D. P. Harmon, coordinator) in providing utility perspectives on reactor maint lance and operations; (4) Management Analysis Company (L. W. Perry, principal) in provide "• the methodology for estimating the overall cost uncertainties of the two reactor concepts; and (5) the U.S. Department of Energy in providing guidance and comments on study emphasis, report organization, and r r esentation of infirmation. Finally, we wish to express our gratitude to Katie Lawhorn of ORNL who, working with the editors, typed numerous iterative drafts of the report, including this final one.

NOTICE This document contains information of a preliminary nature. it is subject to revision or correction and therefore does not represent a final report. *UCND Computer Sciences D i v i s i o n .-_ _ ~ NOTICE mi s aport was prepared as an account of work sponsored by the United States Governmcnt. Neither the United States nor the United Stater Department of Energy, nor any of their employees, nor any of their contractors, subcontractors. or their employees, makes any warranty, expcess or implied, or assumes any legal liability 01 rcrponribUty for the accuracy, completeness or usefulness oi any information, apparatus, product or proms discloud. or represents that its uoe would not rnirinee mivately owned np)lts.