Volume 110
Number 3
Dynamics and Power Prediction in Fission Bursts
Nuclear Science and Engineering / Volume 110 / Number 3 / March 1992 / Pages 209-236
Technical Paper / dx.doi.org/10.13182/NSE90-149
Nuclear Science and Engineering / Volume 110 / Number 3 / March 1992 / Pages 237-253
Technical Paper / dx.doi.org/10.13182/NSE92-A23896
Unbiased Combinations of Nonanalog Monte Carlo Techniques and Fair Games
Nuclear Science and Engineering / Volume 110 / Number 3 / March 1992 / Pages 254-261
Technical Paper / dx.doi.org/10.13182/NSE92-A23897
Boundary Conditions to Describe the Reactor Reflector
Nuclear Science and Engineering / Volume 110 / Number 3 / March 1992 / Pages 262-274
Technical Paper / dx.doi.org/10.13182/NSE92-A23898
Distributed Neutron Sources in a Semi-Infinite Medium
Nuclear Science and Engineering / Volume 110 / Number 3 / March 1992 / Pages 275-281
Technical Paper / dx.doi.org/10.13182/NSE92-A23899
Absolute Measurements of the Fast Neutron Capture Cross Section of 238U
Nuclear Science and Engineering / Volume 110 / Number 3 / March 1992 / Pages 282-288
Technical Paper / dx.doi.org/10.13182/NSE90-99
Differential Neutron Production Cross Sections for 256-MeV Protons
Nuclear Science and Engineering / Volume 110 / Number 3 / March 1992 / Pages 289-298
Technical Paper / dx.doi.org/10.13182/NSE92-A23901
Neutron Yields from Stopping-Length Targets for 256-MeV Protons
Nuclear Science and Engineering / Volume 110 / Number 3 / March 1992 / Pages 299-301
Technical Note / dx.doi.org/10.13182/NSE92-A23902
