Call Number (LC) Title Results
E 1.99:conf-791058--57 Denatured fuel cycles 1
E 1.99:conf-791058--58 Fast-neutron capture cross sections of importance in technological applications. [Review] 1
E 1.99:conf-791058--59 Status of neutron dosimetry and damage analysis for the fusion materials program 1
E 1.99:conf-791058--60 Discrepancy between differential and integral results for the <sup>63</sup>Cu(n,α)<sup>60</sup>Co cross sections. [Threshold to 10 MeV] 1
E 1.99:conf-791058--61 Total-neutron cross sections of heavy nuclei. [30 to 4800 keV] 1
E 1.99:conf-791058--62 Evaluation of /sup 235/U(n,f) above 100 keV for ENDF/B-V and the implications of a unified /sup 235/U mass scale. [Above 100 keV] 1
E 1.99: conf-791058-63 Use of high resolution. gamma. -ray spectroscopy for neutron cross sections 1
E 1.99:conf-791058--64 Measured and evaluated bismuth data for fusion-fission-hybrid and electro-nuclear breeding applications. [1 to 5 MeV] 1
E 1.99:conf-791058--65 Measurement of the fast neutron capture cross section of <sup>238</sup>U relative to <sup>235</sup>U(n,f) 1
E 1.99: conf-791058-66 Burning nuclear wastes in fusion reactors 1
E 1.99:conf-791058--67 Neutron cross section measurements at ORELA 1
E 1.99:conf-791058--68 Use of thorium in fast breeder reactors 1
E 1.99:conf-791058--69 Deep penetration integral experiment for a thorium blanket mockup 1
E 1.99:conf-791058--70 Evaluated data collections from ENSDF. [ORNL] 1
E 1.99:conf-791058--71 Fission product decay heat for thermal reactors 1
E 1.99:conf-791058--72 Measurement of the 2. 35 MeV window in O + n 1
E 1.99:conf-791058--73 Neutron total cross section of <sup>233</sup>U from 0. 01 to 1. 0 eV 1
E 1.99:conf-791058--74 Integral experiments for fusion reactor design analysis. 1
E 1.99:conf-791058--75 Shielding of fusion reactors 1
E 1.99:conf-791059--1 Extraction and recovery of polycyclic aromatic hydrocarbons from highly sorptive matrices such as fly ash 1