LAURIN DODD REFERENCE DOCUMENTS BOX 43 Alternatives for Managing Wastes from Reactors and Post-Fission Operations in the LWR Fuel Cycle - 5/76 Computational Benchmark Problem forDeep Penetration in Iron - LNLL - 1/80 The Development & Appl. of a Coupled Monte Carlo Neutron-Photon Transport Code - 7/72 A Review of the Theory & Application of Monte Carlo Methods - Seminar ORNL 4/80 Vectorized Monte Carlo Photon Transport - LNLL - 5/83 Implementation of DYMACSys. at New Los Alamos Plutonium Processing Facility - 8/82 Calculated Critical Parameters in Simple Geometries for Oxide & Nitrate Water Mixtures of U-233, U-235 and Pu-239 with Thorium - 11/79 RSIC Computer Code Collection - 4/77 International Conference on Design and Safety of Advanced NPPs - 4 volumns - 10/92 Production of Actinide Isotopes in Simulated PWR Fuel and Their Influence on Inherent - Neutron Emission - 7/82 Reactor Safety Research - Semiannual Report 1-6/86 Columbia River Basin Fish & Wildlife Program - 1987 A Measurementof the Capture toFission Ratio for 239Pu - 11/69 Evaluation of Neutron Cross Sections for 244Cm, 246Cm, and 248Cm - 1/77 A Survey of Published Values of int he Fast Fission of U238 - 6/60 AEC Research and Development Report - 12/59 Actnide Newsletter - 3.81 U238 Cross Sections & Their Temperature Depdendence - 6/58 Low-Energy Neutron Resonance Parameters of 238U - 3/66 fe ce fe a ae fe a fe ake he 2c akc He 2fe ae akc age 2fe 29 ae ake ae fe 2h ake fe a 2fe ae he 2 fe ake afc he he afc abe iC ae 2h ae a afc 2h akc 24 akc fe ate ate af 2h ak ade fe 2c ate afe afc abe ae 2 ae afc ae ae afc 3c he a ae