Call Number (LC) Title Results
E 1.99:ornl-5408/r1 Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory Garden Carrier No. 2. Revision 1 1
E 1.99:ornl--5409 Safety analysis report for packaging (SARP) of the Oak Ridge National Laboratory TRU Californium Shipping Container 1
E 1.99:ornl-5409/r1 Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory TRU Californium Shipping Container 1
E 1.99:ornl-5410 Formation of iron carbonyl between a 1/2% Mo steel and high-pressure gases containing carbon monoxide 1
E 1.99:ornl-5411 Carcinogenic risk of lead-210 and polonium-210 in tobacco smoke a selected, annotated bibliography. 1
E 1.99:ornl-5412 Gas-Cooled Reactor Programs. High-Temperature Gas-Cooled Reactor Base-Technology Program. Annual progress report for period ending December 31, 1977 1
E 1.99:ornl-5414 Experimental determinations of the pre- and postirradiation thermal transport and thermal expansion properties of simulated fuel rods for an HTGR 1
E 1.99:ornl-5415 Transuranium processing plant semiannual report of production, status, and plans for period ending December 31, 1977 1
E 1.99:ornl-5418 Chemical separation of boron isotopes 1
E 1.99:ornl-5420 Industrial safety and applied health physics. Annual report for 1977 1
E 1.99:ornl-5422 Postirradiation examination of recycle test elements from the Peach Bottom Reactor 1
E 1.99:ornl-5423 High-temperature gas-cooled reactor fuel recycle development. Annual progress report for period ending September 30, 1977 1
E 1.99:ornl-5426 Gas-cooled reactor programs. Gas-cooled fast reactor program. Annual progress report, 31 Dec 1977 1
E 1.99:ornl-5427 Health and Safety Research Division progress report for period ending April 30, 1978 1
E 1.99:ornl-5428 Operation and postirradiation examination of ORR capsule OF-2 accelerated testing of HTGR fuel. 1
E 1.99:ornl-5431 Effect of oxidizing environment on mechanical properties of molybdenum and TZM 1
E 1.99:ornl-5434 Method for estimating the lattice thermal conductivity of metallic alloys 1
E 1.99:ornl-5436 Organ dose estimates for the Japanese atomic-bomb survivors 1
E 1.99:ornl-5437 Metals and Ceramics Division materials science annual progress report for period ending June 30, 1978 1
E 1.99:ornl-5438 Nitrogen oxide absorption into water and dilute nitric acid in an engineering-scale sieve-plate column description of a mathematical model and comparison with experimental data. 1