Number 1 | Number 2 | Number 3
Neutronic Feasibility Assessment of Liquid Salt-Cooled Pebble Bed Reactors
Nuclear Science and Engineering / Volume 168 / Number 1 / May 2011 / Pages 1-22
Technical Paper / dx.doi.org/10.13182/NSE10-38
Detailed Design of 242mAm Breeding in Pressurized Water Reactors
Nuclear Science and Engineering / Volume 168 / Number 1 / May 2011 / Pages 23-36
Technical Paper / dx.doi.org/10.13182/NSE09-43
Newton's Method for the Computation of k-Eigenvalues in SN Transport Applications
Nuclear Science and Engineering / Volume 168 / Number 1 / May 2011 / Pages 37-58
Technical Paper / dx.doi.org/10.13182/NSE10-01
An Analysis of Reflector Homogenization Techniques for Full Core Diffusion Calculations
Nuclear Science and Engineering / Volume 168 / Number 1 / May 2011 / Pages 59-72
Technical Paper / dx.doi.org/10.13182/NSE10-44
Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 75-92
Technical Paper / dx.doi.org/10.13182/NSE10-50
Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 93-114
Technical Paper / dx.doi.org/10.13182/NSE10-60
On the Accuracy of a Common Monte Carlo Surface Flux Grazing Approximation
Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 115-127
Technical Paper / dx.doi.org/10.13182/NSE09-72
Perspectives on Advanced Simulation for Nuclear Reactor Safety Applications
Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 128-137
Technical Paper / dx.doi.org/10.13182/NSE10-85
Calculation of the Void Fraction and Void Coefficient in an Aqueous Homogeneous Reactor
Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 138-150
Technical Paper / dx.doi.org/10.13182/NSE11-45
Calculation and Analysis of Neutron-Induced Reactions on 59Co up to 200 MeV
Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 151-163
Technical Paper / dx.doi.org/10.13182/NSE09-001
Measuring (n, f) Cross Sections of Short-Lived States
Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 164-171
Technical Paper / dx.doi.org/10.13182/NSE10-19
Tritium Battery with Solid Dielectric
Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 172-179
Technical Paper / dx.doi.org/10.13182/NSE10-49
Interpolation of Temperature-Dependent Nuclide Data in MCNP
Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 180-184
Technical Note / dx.doi.org/10.13182/NSE10-76
Evaluation of Dynamic Pressures from Steam Explosions Applied to Advanced Light Water Reactors
Nuclear Science and Engineering / Volume 168 / Number 3 / July 2011 / Pages 185-196
Technical Paper / dx.doi.org/10.13182/NSE10-24
Nuclear Science and Engineering / Volume 168 / Number 3 / July 2011 / Pages 197-225
Technical Paper / Geometric Convergence of Adaptive Monte Carlo Algorithms for Radiative Transport Problems Based on Importance Sampling Methods / dx.doi.org/10.13182/NSE10-29
Adjoint-Weighted Tallies for k-Eigenvalue Calculations with Continuous-Energy Monte Carlo
Nuclear Science and Engineering / Volume 168 / Number 3 / July 2011 / Pages 226-241
Technical Paper / dx.doi.org/10.13182/NSE10-22
Using Core Symmetry in Monte Carlo Dominance Ratio Calculations
Nuclear Science and Engineering / Volume 168 / Number 3 / July 2011 / Pages 242-247
Technical Paper / dx.doi.org/10.13182/NSE10-37
Stochastic Invariant Imbedding Theory for a Distributed Internal Source
Nuclear Science and Engineering / Volume 168 / Number 3 / July 2011 / Pages 248-264
Technical Paper / dx.doi.org/10.13182/NSE10-08
Deterministic and Stochastic Evaluation of Criticality Excursion Power Bursts
Nuclear Science and Engineering / Volume 168 / Number 3 / July 2011 / Pages 265-277
Technical Paper / dx.doi.org/10.13182/NSE10-11
Simplified Simulation of Fast Neutron Scattering for an Explosives Detection Application
Nuclear Science and Engineering / Volume 168 / Number 3 / July 2011 / Pages 278-286
Technical Paper / dx.doi.org/10.13182/NSE10-13
An Experimental Study on Radon Adsorption Ability and Microstructure of Activated Carbon
Nuclear Science and Engineering / Volume 168 / Number 3 / July 2011 / Pages 287-292
Technical Note / dx.doi.org/10.13182/NSE10-65