Volume 117
Number 2
Nuclear Science and Engineering / Volume 117 / Number 2 / June 1994 / Pages 77-87
Technical Paper / dx.doi.org/10.13182/NSE94-A20074
Nucleon Double-Differential Cross Section Based on Anisotropic Intranuclear Scattering
Nuclear Science and Engineering / Volume 117 / Number 2 / June 1994 / Pages 88-98
Technical Paper / dx.doi.org/10.13182/NSE94-A20075
Double-Differential Cross Section of Light Composite Particles in the Exciton Model
Nuclear Science and Engineering / Volume 117 / Number 2 / June 1994 / Pages 99-109
Technical Paper / dx.doi.org/10.13182/NSE93-66
The Use of an Expanded Polynomial Orthogonal Set in Approximations to Gamma-Ray Buildup Factor Data
Nuclear Science and Engineering / Volume 117 / Number 2 / June 1994 / Pages 110-120
Technical Paper / dx.doi.org/10.13182/NSE94-A20077
Solution of Depletion Chain Equations Using Nonsingular Bateman Coefficients
Nuclear Science and Engineering / Volume 117 / Number 2 / June 1994 / Pages 121-125
Technical Paper / dx.doi.org/10.13182/NSE94-A20078
Countercurrent Gas-Liquid Flow in a Pressurized Water Reactor Hot Leg
Nuclear Science and Engineering / Volume 117 / Number 2 / June 1994 / Pages 126-133
Technical Paper / dx.doi.org/10.13182/NSE94-A20079
Impurity Characterization of Si1−xGex Circuit Structures with the Use of Neutron Activation Analysis
Nuclear Science and Engineering / Volume 117 / Number 2 / June 1994 / Pages 134-139
Technical Note / dx.doi.org/10.13182/NSE94-A20080
