Number 1 | Number 2 | Number 3
Performance Modeling of Parallel Algorithms for Solving Neutron Diffusion Problems
Nuclear Science and Engineering / Volume 120 / Number 1 / May 1995 / Pages 1-17
Technical Paper / dx.doi.org/10.13182/NSE95-A24102
Physics Characteristics of Nuclear Power Systems with Reduced Long-Term Radioactivity Risk
Nuclear Science and Engineering / Volume 120 / Number 1 / May 1995 / Pages 18-39
Technical Paper / dx.doi.org/10.13182/NSE95-A24103
Thick-Target Neutron Yield for Charged Particles
Nuclear Science and Engineering / Volume 120 / Number 1 / May 1995 / Pages 40-54
Technical Paper / dx.doi.org/10.13182/NSE95-A24104
Inelastic Neutron Scattering by 235U and 238U Nuclei
Nuclear Science and Engineering / Volume 120 / Number 1 / May 1995 / Pages 55-64
Technical Paper / dx.doi.org/10.13182/NSE120-55
Behavior and Removal of Radionuclides Generated in the Cooling Water of a Proton Accelerator
Nuclear Science and Engineering / Volume 120 / Number 1 / May 1995 / Pages 65-71
Technical Paper / dx.doi.org/10.13182/NSE95-A24106
P1, P2 and Asymptotic Approximations for Stochastic Transport
Nuclear Science and Engineering / Volume 120 / Number 2 / June 1995 / Pages 75-90
Technical Paper / dx.doi.org/10.13182/NSE95-A24109
Nuclear Science and Engineering / Volume 120 / Number 2 / June 1995 / Pages 91-101
Technical Paper / dx.doi.org/10.13182/NSE95-A24110
Nuclear Science and Engineering / Volume 120 / Number 2 / June 1995 / Pages 102-109
Technical Paper / dx.doi.org/10.13182/NSE95-A24111
One-Dimensional Diffusion Theory Kinetics in RELAP5
Nuclear Science and Engineering / Volume 120 / Number 2 / June 1995 / Pages 110-123
Technical Paper / dx.doi.org/10.13182/NSE95-A24112
Nuclear Science and Engineering / Volume 120 / Number 2 / June 1995 / Pages 124-135
Technical Paper / dx.doi.org/10.13182/NSE95-A24113
Systematics in Differential Thick-Target Neutron Yields Parameterized by Moving Source Model
Nuclear Science and Engineering / Volume 120 / Number 2 / June 1995 / Pages 136-145
Technical Note / dx.doi.org/10.13182/NSE95-A24114
Nuclear Science and Engineering / Volume 120 / Number 3 / July 1995 / Pages 147-164
Technical Paper / dx.doi.org/10.13182/NSE95-A24116
Nuclear Science and Engineering / Volume 120 / Number 3 / July 1995 / Pages 165-186
Technical Paper / dx.doi.org/10.13182/NSE95-A24117
Anisotropic Scattering Treatment for the Neutron Transport Equation with Primal Finite Elements
Nuclear Science and Engineering / Volume 120 / Number 3 / July 1995 / Pages 187-198
Technical Paper / dx.doi.org/10.13182/NSE95-A24118
Nuclear Science and Engineering / Volume 120 / Number 3 / July 1995 / Pages 199-210
Technical Paper / dx.doi.org/10.13182/NSE95-A24119
Nuclear Science and Engineering / Volume 120 / Number 3 / July 1995 / Pages 211-222
Technical Paper / dx.doi.org/10.13182/NSE95-A24120
Neutron Temperature Measurements in a Cryogenic Hydrogenous Moderator
Nuclear Science and Engineering / Volume 120 / Number 3 / July 1995 / Pages 223-230
Technical Paper / dx.doi.org/10.13182/NSE95-A24121