Volume 152
Number 3
Analog Monte Carlo Methods for Simulating Isotopic Inventories in Complex Systems
Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 243-255
Technical Paper
Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 256-273
Technical Paper
Stochastic Approximation for Monte Carlo Calculation of Steady-State Conditions in Thermal Reactors
Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 274-283
Technical Paper
Thermal Neutron Diffusion in an Array of Plates
Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 284-291
Technical Paper
Analysis of Single Rod Drop Transient in BWR Considering Detailed Intrabundle Void Distribution
Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 292-305
Technical Paper
Use of 240Pu Waste as a Burnable Absorber in Light Water Reactors
Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 306-313
Technical Paper
Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 314-319
Technical Paper
Determination of Intermediate Energy Neutron Cross Sections Using the Ramsauer Model
Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 320-324
Technical Paper
Calculation and Evaluation of Neutron-Induced Reactions on 58Ni Below 150 MeV
Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 325-333
Technical Note
A Rule for Determining Fissile Isotopes
Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 334-335
Technical Note