Volume 170
Number 1 | Number 2 | Number 3
Number 1
Approximate Solution and Application of the Survival Probability Diffusion Equation
Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 1-15
Technical Papers
Proliferation-Resistant Fuel for CANDU Reactors
Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 16-26
Technical Papers
Chaotic Data Encryption for Long-Distance Monitoring of Nuclear Reactors
Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 27-43
Technical Papers
)233Th, 98Mo(n,Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 44-53
Technical Papers
Peelle's Pertinent Puzzle: A Fake Due to Improper Analysis
Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 54-60
Technical Papers
Studies on Production of Neutrons in the Spallation Reactions Using the Monte Carlo Code MCNPX
Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 61-65
Technical Papers
Correcting the Cusping Problem in Three-Dimensional Transients Through NEM Modification
Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 66-74
Technical Notes
On the Method ASCM for the Solution of the External Source Problem in a Slightly Subcritical Reactor
Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 75-86
Technical Notes
Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 87-97
Technical Notes
Highly Efficient, Exact Quadratures for Three-Dimensional Discrete Ordinates Transport Calculations
Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 98-101
Technical Notes
Number 2
Nuclear Science and Engineering / Volume 170 / Number 2 / February 2012 / Pages 103-124
Parallel Fission Bank Algorithms in Monte Carlo Criticality Calculations
Nuclear Science and Engineering / Volume 170 / Number 2 / February 2012 / Pages 125-135
A Probabilistic Physics-of-Failure Approach to Prediction of Steam Generator Tube Rupture Frequency
Nuclear Science and Engineering / Volume 170 / Number 2 / February 2012 / Pages 136-150
Nuclear Science and Engineering / Volume 170 / Number 2 / February 2012 / Pages 151-167
Gradient-Enhanced Universal Kriging for Uncertainty Propagation
Nuclear Science and Engineering / Volume 170 / Number 2 / February 2012 / Pages 168-195
A Technique for Accounting for Multigroup Cross-Section Interdependence in Sensitivity Calculations
Nuclear Science and Engineering / Volume 170 / Number 2 / February 2012 / Pages 196-206
Number 3
Nuclear Science and Engineering / Volume 170 / Number 3 / March 2012 / Pages 207-233
Technical Paper
Kernel Density Estimation Method for Monte Carlo Global Flux Tallies
Nuclear Science and Engineering / Volume 170 / Number 3 / March 2012 / Pages 234-250
Technical Paper
An Innovative Method to Measure the Gamma-Ray Emission Probabilities in the Decay of 238Np and 233Pa
Nuclear Science and Engineering / Volume 170 / Number 3 / March 2012 / Pages 251-264
Technical Paper
Evaluation and Adjustment of the Neutron-Induced Reactions of 63,65Cu
Nuclear Science and Engineering / Volume 170 / Number 3 / March 2012 / Pages 265-279
Technical Paper
Nuclear Science and Engineering / Volume 170 / Number 3 / March 2012 / Pages 280-289
Technical Paper
Core Temperature Monitoring System for Prototype Fast Breeder Reactor
Nuclear Science and Engineering / Volume 170 / Number 3 / March 2012 / Pages 290-293
Technical Paper
