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Volume 183

Number 2

A Method for the Adaptive Selection of Angular Flux Expansion Orders in the Coarse Mesh Radiation Transport (COMET) Method

Kyle Remley, Farzad Rahnema

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 161-172

Technical Paper / dx.doi.org/10.13182/NSE15-97

Optimization Algorithms for Multigroup Energy Structures

M. J. Fleming, L. W. G. Morgan, E. Shwageraus

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 173-184

Technical Paper / dx.doi.org/10.13182/NSE15-55

A New Nodal Expansion Method with High-Order Moments for the Reduction of Numerical Oscillation in Convection-Diffusion Problems

Xiafeng Zhou, Jiong Guo, Fu Li

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 185-195

Technical Paper / dx.doi.org/10.13182/NSE15-95

Convergence Analysis for the Method of Characteristics in Unstructured Meshes

Richard Sanchez, Simone Santandrea

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 196-213

Technical Paper / dx.doi.org/10.13182/NSE15-78

Stochastic Analog Neutron Transport with TRIPOLI-4 and FREYA: Bayesian Uncertainty Quantification for Neutron Multiplicity Counting

J. M. Verbeke, O. Petit

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 214-228

Technical Paper / dx.doi.org/10.13182/NSE15-82

Nuclear Reactor Transient Analysis by Continuous-Energy Monte Carlo Calculation Based on Predictor-Corrector Quasi-Static Method

YuGwon Jo, Bumhee Cho, Nam Zin Cho

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 229-246

Technical Paper / dx.doi.org/10.13182/NSE15-100

Assessment of the Online Core Power Measured by a Boron Chamber in a Pool-Type Research Reactor Using a Nonlinear Calibration Model

L. Pantera, Y. Garnier, F. Jeury

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 247-260

Technical Paper / dx.doi.org/10.13182/NSE15-77

Sensitivity of Cross Sections to Isotopic Densities for Subgroup Resonance Self-Shielding Calculations

M. Dion, G. Marleau

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 261-274

Technical Paper / dx.doi.org/10.13182/NSE15-60

Preequilibrium Models for 63Cu(n, xp) Reaction in Neutrons at 9, 11, 14.8, and 15 MeV Using the EMPIRE 3.2 Code

L. Yettou

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 275-285

Technical Paper / dx.doi.org/10.13182/NSE15-73

Neutron Total Cross Sections and Resonance Parameters of Palladium

Taofeng Wang, Guinyun Kim, Young Do Oh, Moo-Hyun Cho, In Soo Ko, Won Namkung

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 286-297

Technical Paper / dx.doi.org/10.13182/NSE15-64

Double-Differential Angle-Dependent Three-Body Neutron Production Cross Sections of the Reaction 2H(t,n)X+Y at Triton Energies Between 5.97 and 16.41 MeV

M. Drosg, G. Haouat, D. M. Drake

Nuclear Science and Engineering / Volume 183 / Number 2 / June 2016 / Pages 298-303

Technical Note / dx.doi.org/10.13182/NSE15-118

 
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