Call Number (LC) Title Results
E 1.99:conf-840901-11 Measurements and analysis of control rod worths in large heterogeneous LMFBR cores 1
E 1.99:conf-840901-13 Flux synthesis for the on-line surveillance of nuclear power plants 1
E 1.99:conf-840901-14 Resolved-resonance neutron widths from a consistent reanalysis of the most recent ²³⁸U transmission data 1
E 1.99:conf-840901-15 Status of nuclear data of importance for LMFBR applications prior to the evaluation of ENDF/B-VI 1
E 1.99:conf-840901-16 Evaluation of the core physics and safety characteristics of a quasi-homogeneous LMFBR concept 1
E 1.99: conf-840901-19 Finite element method for solving neutron transport problems 1
E 1.99:conf-840901-21 Physics implications of oxide and metal fuel on the design of small LMFBR cores 1
E 1.99: conf-840902-3 Radiation field associated with Hiroshima and Nagasaki 1
E 1.99:conf-840902-4 Recent developments in neutron dosimetry and damage calculations for fusion materials irradiations 1
E 1.99:conf-840902-5 Fluence, dosimetry, and steel-dpa rates in EBR-II 1
E 1.99:conf-840902-6 Recent progress and developments in LWR-PV calculational methodology 1
E 1.99:conf-840902-7 Data acquisition and control system for the K/sub 1C/-HSST experiments at the ORR 1
E 1.99:conf-840902-8 Calculated spectral fluences and dosimeter activities for the metallurgical blind test irradiations at the ORR-PSF. [PWR] 1
E 1.99:conf-840902-9 Calculation of the neutron source distribution in the VENUS PWR Mockup Experiment 1
E 1.99:conf-840902-10 LSL-M1 and LSL-M2 two extensions of the LSL adjustment procedure for including multiple spectrum locations. 1
E 1.99:conf-840902-11 ORNL evaluation of the ORR-PSF metallurgical experiment and blind test 1
E 1.99: conf-840902-13 Characterization of fuel distributions in the Three-Mile Island Unit 2 (TMI-2) reactor system by neutron and gamma-ray dosimetry 1
E 1.99:conf-840902-22 Unfolded ANO-1 fluxes using the LEPRICON methodology. [Least-squares EPRI CONsolidation] 1
E 1.99:conf-840905-1 National need for utilizing nuclear energy for process heat generation 1
E 1.99: conf-840906-1 Fast neutron capture with a white neutron source 1