R-Matrix Analysis of the 240Pu Neutron Cross Sections in the Thermal to 5700-eV Energy Range
Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 105-129
Technical Paper / dx.doi.org/10.13182/NSE127-105
Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 130-138
Technical Paper / dx.doi.org/10.13182/NSE97-A28592
A Composite Nodal Finite Element for Hexagons
Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 139-153
Technical Paper / dx.doi.org/10.13182/NSE97-A28593
Variational Nodal Transport Methods with Heterogeneous Nodes
Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 154-168
Technical Paper / dx.doi.org/10.13182/NSE97-A28594
Discrete Ordinates Methods in xy Geometry with Spatially Varying Angular Discretization
Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 169-181
Technical Paper / dx.doi.org/10.13182/NSE97-A28595
A Non-Gaussian Treatment of Radiation Pencil Beams
Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 182-198
Technical Paper / dx.doi.org/10.13182/NSE97-A28596
Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 199-219
Technical Paper / dx.doi.org/10.13182/NSE97-A28597
Heat Transfer Characteristics of Reflux Condensation Phenomena in a Single Vertical Tube
Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 220-229
Technical Paper / dx.doi.org/10.13182/NSE97-A28598
Neutron Skyshine Calculations with the Integral Line-Beam Method
Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 230-237
Technical Note / dx.doi.org/10.13182/NSE97-A28599
Multiple Recycling of Light Water Reactor Waste Plutonium in a Fast Spectrum Core
Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 238-244
Technical Note / dx.doi.org/10.13182/NSE97-A28600