Call Number (LC) Title Results
E 1.99:ga-a-13833 Thorium utilization program quarterly progress report for the period ending February 29, 1976. [HTGR Fuel Recycle] 1
E 1.99:ga-a-13835 Solvent extraction in HTGR reprocessing. Interim development report 1
E 1.99:ga-a-13839 Analysis of fission product behavior in the Saclay Spitfire Loop Test SSL-1. [HTGR] 1
E 1.99:ga-a-13860 HTGR spent reflector block disposal study. [Burial or crush-burn processing] 1
E 1.99:ga-a-13861 Fatigue tests of dowel-socket systems. [HTGR] 1
E 1.99:ga-a-13886(vol.1) HTGR spent fuel composition and fuel element block flow 1
E 1.99:ga-a-13903 Safety analysis report for Fort. St. Vrain test elements FTE-1 through FTE-8. Proposed supplement to the Final Safety Analysis Report for Fort St. Vrain Nuclear Generating Station 1
E 1.99:ga-a-13907(vol.1) Operating history report for the Peach Bottom HTGR. Volume I. Reactor operating history 1
E 1.99:ga-a-13907(vol.2) Operating History Report for the Peach Bottom HTGR. Volume II. Test element operating history 1
E 1.99:ga-a-13917 Mechanical tests of full-size Fort St. Vrain fuel blocks 1
E 1.99:ga-a-13941 HTGR fuels and core development program. Quarterly progress report for the period ending May 31, 1976. [Graphite and fuels irradiation; fission product release] 1
E 1.99:ga-a-13943 Postirradiation examination and evaluation of Peach Bottom fuel test element FTE-6 1
E 1.99:ga-a-13944 Postirradiation examination and evaluation of Peach Bottom fuel test elements FTE-14 and FTE-15 1
E 1.99:ga-a-13949 Thorium utilization program. Quarterly progress report for the period ending May 31, 1976. [Fuel element crushing, solids handling, fluidized-bed combustion, aqueous separations, solvent extraction, off-gas studies, semiremote handling systems, alternative head-end processing, and fuel recycle design] 1
E 1.99:ga-a-13955 Statistical study of the strength of near-isotropic graphite 1
E 1.99:ga-a-13990 Cesium transport data for HTGR systems 1
E 1.99:ga-a-14011(vol.1) HTGR plant availability and reliability evaluations. Volume I. Summary of evaluations 1
E 1.99:ga-a-14011(vol.2) HTGR plant availability and reliability evaluations. Volume II. Appendices 1
E 1.99:ga-a-14016 Radioisotope space power generator annual report, July 1, 1974--June 30, 1975. [TPM-217 P-type material and SiGe technology] 1
E 1.99:ga-a-14021 Conceptual design of the blanket and power conversion system for a mirror hybrid fusion-fission reactor. 12-month progress report, July 1, 1975--June 30, 1976 1