Call Number (LC) Title Results
E 1.99:conf-791058--36 Calculated particle production spectra and multiplicities from nucleon-fissile element collisions at medium energies 1
E 1.99:conf-791058--37 Evaluation of the fission and capture cross sections of <sup>240</sup>Pu; and <sup>241</sup>Pu for ENDF/B-V. [10/sup -5/ eV to 20 MeV] 1
E 1.99:conf-791058--38 High-resolution fission cross section of <sup>231</sup>Pa. [0. 4 eV to 12 MeV] 1
E 1.99:conf-791058--39 Neutron total cross section measurements on <sup>249</sup>Cf. [0. 01 to 90 eV] 1
E 1.99: conf-791058-40 Evaluations of the ⁵⁸Fe(n,. gamma. )⁵⁹Fe, and ⁵⁴Fe(n,p)⁵⁴Mn reactions for the ENDF/B-V dosimetry file. [E < 15 MeV] 1
E 1.99: conf-791058-41 Measurements of neutron spectra from 35 MeV deuterons on thick lithium for the FMIT facility 1
E 1.99: conf-791058-42 Evaluations of fission product capture cross sections for ENDF/B-V 1
E 1.99: conf-791058-43 Nuclear data needs for FMIT 1
E 1.99: conf-791058-44 Coupled channels model for radiative capture of nucleons by ¹²C. [1 to 10 MeV] 1
E 1.99: conf-791058-45 Neutron spectrum at 90/sup 0/ from 800 MeV (p,n) reactions on a Ta target 1
E 1.99: conf-791058-46 Capture cross section and gamma-ray spectrum calculations for medium-weight nuclei. [Double-peak, energy-dependent Breit-Wigner model] 1
E 1.99: conf-791058-47 Spatial dependence of flux and damage in the FMIT test cell 1
E 1.99:conf-791058--48 Fission cross section of <sup>239</sup>Th and <sup>232</sup>Th relative to <sup>235</sup>U 1
E 1.99: conf-791058-49 Finite element basis used in consistent nuclear data evaluation 1
E 1.99: conf-791058-50 Beta and gamma decay heat evaluation for the thermal fission of ²³⁵U 1
E 1.99: conf-791058-51 Stellar nucleosynthesis and the 24-keV neutron capture cross sections of some heavy nuclei 1
E 1.99: conf-791058-52 Doppler broadening effect to neutron resonance cross sections for Ag, AgCl, and Ag/sub 2/O. [Yield, Debye temperature] 1
E 1.99:conf-791058--54 Photoneutron leakage from the W(gamma,n) reaction at radiation therapy centers 1
E 1.99:conf-791058--55 Fast-neutron total and scattering cross sections of Cr, Fe and <sup>60</sup>Ni. [1 to 4. 5 MeV] 1
E 1.99:conf-791058--56 Neutron dosimetry for radiation damage in fission and fusion reactors 1