Call Number (LC) Title Results
E 1.99:ornl/sub-4390/4 400-MWe consolidated nuclear steam system (CNSS) 1200-MWt/conceptual design. 1
E 1.99:ornl/sub-4390/5 Duval Corporation application study nuclear process energy from PE-CNSG. [Sulfur mining] 1
E 1.99: ornl/sub-4390/6 400-MWe Consolidated Nuclear Steam System (CNSS). 1200-MWt Phase 2A interim studies. [PWR] 1
E 1.99:ornl/sub/4403-1 Endochronic theory for inelasticity and failure analysis of concrete structures 1
E 1.99:ornl/sub-4415 Evaluation of hydrologic isolation from evidence in mine openings in igneous and metamorphic rocks in the Maritime Provinces of Canada 1
E 1.99:ornl-sub-4450-1 Water tests for determining post voiding behavior in the LMFBR 1
E 1.99:ornl/sub-4496/1 Geologic feasibility of talc and serpentinite bodies from the Appalachian Mountain Region of eastern United States with regard to siting of radioactive-waste repositories. Final report 1
E 1.99:ornl/sub/7010-1 Possible salt mine and brined cavity sites for radioactive waste disposal in the northeastern southern peninsula of Michigan. [Seven possible sites are considered on the basis of listed criteria] 1
E 1.99:ornl/sub-7015/1 Stress intensities for nozzle cracks in reactor vessels. Reporting period, January 1, 1976--October 31, 1976. [PWR and BWR] 1
E 1.99:ornl/sub--7117/1 TNS quarterly progress report for the period April, May, June (1976) 1
E 1.99:ornl/sub-7117/5 TNS quarterly progress report, January--March 1977 1
E 1.99:ornl/sub-7117/6 TNS quarterly progress report, April--June 1977 1
E 1.99:ornl/sub--7117/9 STRESS ANALYSIS OF THE CONCEPTUAL DESIGN CONFIGURATIONS OF CONSTANT TENSION D-SHAPED SUPERCONDUCTING TOROIDAL FIELD COILS FOR TNS 1
E 1.99:ornl/sub-7117/15 Engineering parameters for four ignition TNS tokamak reactor systems 1
E 1.99:ornl/sub-7117/24 TNS engineering trade study analysis 1
E 1.99:ornl/sub-7117/25 Four ignition TNS tokamak reactor systems design summary. 1
E 1.99:ornl/sub-7117/26 Improved bundle divertor design for ISX-B 1
E 1.99:ornl/sub--7117/27 LOW-COST IGNITION DEMONSTRATION REACTOR (IDR) SCOPING STUDY 1
E 1.99:ornl/sub-7164/1 Experimental studies concerning the drying of voloxidizer off-gases 1
E 1.99:ornl/sub-7167/1 Applicability of a generic monitoring program for radioactive waste burial grounds at Oak Ridge National Laboratory and Idaho National Engineering Laboratory 1