Call Number (LC) Title Results
E 1.99: conf-731101--8 Computerized system for ultralow temperature polarized nuclei time reversal and parity experiments 1
E 1.99: conf-731101--9 Fission gas and void volume measuring system 1
E 1.99: conf-731101--10 Improved heat transfer from radioactive waste canisters 1
E 1.99:conf-731101--12 Selection of group energy boundaries using sensitivity theory 1
E 1.99:conf-731101--13 Remote maintenance experience in the Transuranium Processing Plant at ORNL 1
E 1.99:conf-731101--14 Validation of Monte Carlo calculations of shipping cask systems 1
E 1.99: conf-731101--16 Mathematical model for the transport of environmental plutonium 1
E 1.99: conf-731101--17 Analysis of internal pressure behavior as a function of vent size in a radioisotopic thermoelectric generator 1
E 1.99: conf-731101--19 Retrievable surface storage of high-level radioactive wastes 1
E 1.99: conf-731101--20 Chemical assay of plutonium for safeguards 1
E 1.99: conf-731101--23 Studies with a passive Ge(Li) assay system 1
E 1.99: conf-731101--25 Durability evaluation of radioactive waste products 1
E 1.99: conf-731101--26 Design improvements in the L-10 shipping container 1
E 1.99:conf-731101--27 ORNL high-temperature structural design methods development program 1
E 1.99:conf-731101--28 Thermal and electrical conductivities and Seebeck coefficients of unirradiated and irradiated graphites from 300 to 1000 K 1
E 1.99: conf-731101--29 Rio Blanco gas quality analysis and evaluation program status report 1
E 1.99:conf-731101--31 Fused-salt corrosion and its prevention in fusion reactors 1
E 1.99:conf-731101--32 Materials problems in the design of magnetically confined plasma fusion reactor 1
E 1.99:conf-731101--33 Thermal conductivity of oriented fibrous carbon insulation from 300 to 1300 K in nitrogen and argon at one atmosphere 1
E 1.99:conf-731101--34 Preparation and characterization of neutron dosimeter materials 1