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 / dx.doi.org/10.13182/NSE06-A2579
Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 256-273
Technical Paper / dx.doi.org/10.13182/NSE06-A2580
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 / dx.doi.org/10.13182/NSE06-2
Thermal Neutron Diffusion in an Array of Plates
Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 284-291
Technical Paper / dx.doi.org/10.13182/NSE06-A2582
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 / dx.doi.org/10.13182/NSE06-A2583
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 / dx.doi.org/10.13182/NSE06-A2584
Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 314-319
Technical Paper / dx.doi.org/10.13182/NSE06-A2585
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 / dx.doi.org/10.13182/NSE06-A2586
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 / dx.doi.org/10.13182/NSE06-A2587
A Rule for Determining Fissile Isotopes
Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 334-335
Technical Note / dx.doi.org/10.13182/NSE06-A2588
