Number 1 | Number 2 | Number 3
Fuel Cycle Options for the Production and Utilization of Denatured Plutonium
Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 1-23
Technical Paper / dx.doi.org/10.13182/NSE07-A2681
Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 24-39
Technical Paper / dx.doi.org/10.13182/NSE07-A2682
Two-Dimensional Modeling of the Direct ECC Bypass in the APR1400 Downcomer
Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 40-54
Technical Paper / dx.doi.org/10.13182/NSE07-A2683
Strategies in Stochastic Transport
Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 55-67
Technical Paper / dx.doi.org/10.13182/NSE07-A2684
The Description of Particle Transport Problems with Helical Symmetry
Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 68-73
Technical Paper / dx.doi.org/10.13182/NSE07-A2685
Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 74-85
Technical Paper / dx.doi.org/10.13182/NSE06-32
Investigations of 238U Captures to Total Fissions in a Westinghouse SVEA-96+ Assembly
Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 86-95
Technical Paper / dx.doi.org/10.13182/NSE07-A2687
Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 96-102
Technical Paper / dx.doi.org/10.13182/NSE07-A2688
The 10B(n,0)/10B(n,
1
) Branching Ratio
Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 103-114
Technical Paper / dx.doi.org/10.13182/NSE07-A2689
Differential Cross-Section Measurement for the 64Zn(n, )61Ni Reaction at 5.03 and 5.95 MeV
Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 115-119
Technical Paper / dx.doi.org/10.13182/NSE07-A2690
Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 121-138
Technical Paper / dx.doi.org/10.13182/NSE07-A2691
Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 139-153
Technical Paper / dx.doi.org/10.13182/NSE05-91
A Discretization Scheme for the Three-Dimensional Angular Fokker-Planck Operator
Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 154-163
Technical Paper / dx.doi.org/10.13182/NSE07-A2693
Nonanalog Implementations of Monte Carlo Isotopic Inventory Analysis
Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 164-179
Technical Paper / dx.doi.org/10.13182/NSE07-A2694
An Optimum Approach to Monte Carlo Burnup
Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 180-196
Technical Paper / dx.doi.org/10.13182/NSE07-A2695
Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 197-210
Technical Paper / dx.doi.org/10.13182/NSE06-14
Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 211-218
Technical Paper / dx.doi.org/10.13182/NSE07-A2697
Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 219-228
Technical Paper / dx.doi.org/10.13182/NSE07-A2698
Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 229-243
Technical Paper / dx.doi.org/10.13182/NSE07-A2699
Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 244-266
Technical Note / dx.doi.org/10.13182/NSE07-A2700
Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 267-279
Technical Note / dx.doi.org/10.13182/NSE07-A2701
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