Volume 156
Number 3
NEPTUNE: A New Software Platform for Advanced Nuclear Thermal Hydraulics
Nuclear Science and Engineering / Volume 156 / Number 3 / July 2007 / Pages 281-324
Technical Paper / dx.doi.org/10.13182/NSE05-98
Spatial Finite-Element Lumping Techniques for the Quadrilateral Mesh Sn Equations in X-Y Geometry
Nuclear Science and Engineering / Volume 156 / Number 3 / July 2007 / Pages 325-342
Technical Paper / dx.doi.org/10.13182/NSE06-13
Analytical Calculation of the Average Dancoff Factor for Prismatic High-Temperature Reactors
Nuclear Science and Engineering / Volume 156 / Number 3 / July 2007 / Pages 343-356
Technical Paper / dx.doi.org/10.13182/NSE07-A2704
Nuclear Science and Engineering / Volume 156 / Number 3 / July 2007 / Pages 357-390
Technical Paper / dx.doi.org/10.13182/NSE156-357
Evaluation of the 238U Neutron Cross Section in the Unresolved Resonance Range
Nuclear Science and Engineering / Volume 156 / Number 3 / July 2007 / Pages 391-402
Technical Paper / dx.doi.org/10.13182/NSE07-A2706
Unbiased Monte Carlo Estimation of the Reciprocal of an Integral
Nuclear Science and Engineering / Volume 156 / Number 3 / July 2007 / Pages 403-407
Technical Paper / dx.doi.org/10.13182/NSE07-A2707
The Common Properties of the "Fertile" Isotopes
Nuclear Science and Engineering / Volume 156 / Number 3 / July 2007 / Pages 408-409
Technical Note / dx.doi.org/10.13182/NSE07-A2708
