Call Number (LC) Title Results
E 1.99:ornl/tm-7923 Methods and procedures for internal radiation dosimetry at ORNL 1
E 1.99:ornl/tm-7925 Performance of a large hyperpure germanium detector array for in-vivo detection of low-energy photon and x-ray emitters analytical procedure and current capabilities. 1
E 1.99:ornl/tm-7927 Calculation of neutron and gamma-ray energy spectra for fusion reactor shield design comparison with Experiment II. 1
E 1.99:ornl/tm-7928 INTDOS a computer code for estimating internal radiation dose using recommendations of the International Commission on Radiological Protection. 1
E 1.99:ornl/tm-7930 Thermal analysis of SYNROC gel microspheres 1
E 1.99:ornl/tm-7935 Review of petroleum transport network models and their applicability to a national refinery model 1
E 1.99:ornl/tm-7940 Absolute measurement of anti. nu. /sub p/ for /sup 252/Cf using the ORNL large liquid scintillator neutron detector 1
E 1.99:ornl/tm-7942 Kinetic model for predicting the concentrations of active halogens species in chlorinated saline cooling waters. Final report 1
E 1.99:ornl/tm-7943 Environmental assessment model for shallow land disposal of low-level radioactive wastes interim report. [PRESTO (Prediction of Radiation Effects from Shallow Trench Operations)] 1
E 1.99:ornl/tm-7945 Representation of the neutron cross sections of several fertile and fissile nuclei in the resonance regions 1
E 1.99:ornl/tm-7948/v1 Fusion Engineering Device design description 1
E 1.99:ornl/tm-7948/vol.2 Fusion engineering device design description 1
E 1.99:ornl/tm-7949 Neutron production by protons (190 to 268 MeV) in a water-cooled tantalum target 1
E 1.99:ornl/tm-7951 Decontamination of transuranic waste metal by melt refining 1
E 1.99:ornl/tm-7957 Compilation of theoretical electron-impact excitation cross sections for Fe atomic ions 1
E 1.99:ornl/tm-7958 Evaluation of tubular ceramic heat exchanger materials in acidic coal ash from coal-oil-mixture combustion. [Sialon; alumina; CVD, sintered, and siliconized SiC] 1
E 1.99:ornl/tm-7962-vol.3 Radiological assessment of radioactive waste-disposal areas at Oak Ridge National Laboratory. Volume 3. Technical background information for the ORNL environmental and safety report 1
E 1.99:ornl/tm-7969 High-water-base hydraulic fluid-irradiation experiments 1
E 1.99:ornl/tm-7970 Metals and Ceramics Division materials science program. Annual progress report for period ending June 30, 1981 1
E 1.99:ornl/tm-7972 Monte Carlo analysis of a time-dependent neutron and secondary gamma-ray integral experiment on a thick concrete and steel shield 1