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Volume 176

Number 1 | Number 2 | Number 3

Number 1

A Priori Deterministic Computational-Cost Optimization Of Weight-Dependent Variance-Reduction Parameters For Monte Carlo Neutral-Particle Transport

C. J. Solomon, A. Sood, T. E. Booth, and J. K. Shultis

Nuclear Science and Engineering / Volume 176 / Number 1 / January 2014 / Pages 1-36

Technical Paper / dx.doi.org/10.13182/NSE12-81

FW-CADIS Method For Global And Regional Variance Reduction Of Monte Carlo Radiation Transport Calculations

John C. Wagner, Douglas E. Peplow, and Scott W. Mosher

Nuclear Science and Engineering / Volume 176 / Number 1 / January 2014 / Pages 37-57

Technical Paper / dx.doi.org/10.13182/NSE12-33

Real Variance Estimation By Grouping Histories In Monte Carlo Eigenvalue Calculations

Hyung Jin Shim, Sung Hoon Choi, and Chang Hyo Kim

Nuclear Science and Engineering / Volume 176 / Number 1 / January 2014 / Pages 58-68

Technical Paper / dx.doi.org/10.13182/NSE12-87

High-Order Perturbation Theory for Incident Flux Response Expansion Methods

Dingkang Zhang and Farzad Rahnema

Nuclear Science and Engineering / Volume 176 / Number 1 / January 2014 / Pages 69-80

Technical Paper / dx.doi.org/10.13182/NSE13-1

Calibration And Improved Prediction Of Computer Models By Universal Kriging

FranÁois Bachoc, Guillaume Bois, Josselin Garnier, and Jean-Marc Martinez

Nuclear Science and Engineering / Volume 176 / Number 1 / January 2014 / Pages 81-97

Technical Paper / dx.doi.org/10.13182/NSE12-55

Measured F(α,n) Yield From 234U In Uranium Hexafluoride

Karen A. Miller, Martyn T. Swinhoe, Stephen Croft,Takayuki Tamura, Shun Aiuchi, Akio Kawai, and Tomonori Iwamoto

Nuclear Science and Engineering / Volume 176 / Number 1 / January 2014 / Pages 98-105

Technical Paper / dx.doi.org/10.13182/NSE12-43

Fission Product Yield In The Neutron-Induced Fission of 232Th With Average Energies of 5.42, 7.75, And 10.09 MeV

P. M. Prajapati, H. Naik, S. Mukherjee, S. V. Suryanarayana, B. S. Shivashankar, R. Crasta, V. K. Mulik, K. C. Jagadeesan, S. V. Thakre, S. Ganesan, and A. Goswami

Nuclear Science and Engineering / Volume 176 / Number 1 / January 2014 / Pages 106-113

Technical Paper / dx.doi.org/10.13182/NSE12-78

Number 2

A Review on Sodium Boiling Phenomena in Reactor Systems

Matthias Vanderhaegen and Alix Le Belguet

Nuclear Science and Engineering / Volume 176 / Number 2 / February 2014 / Pages 115-137

Technical Paper / dx.doi.org/10.13182/NSE12-99

Numerical Study of Compact Heat Exchanger Designs for Generation IV Supercritical Carbon Dioxide Power Conversion Cycles

Bryce K. Y. Matsuo, Mark Anderson, and Devesh Ranjan

Nuclear Science and Engineering / Volume 176 / Number 2 / February 2014 / Pages 138-153

Technical Paper / dx.doi.org/10.13182/NSE12-85

Numerical Solutions of the Poisson Equation: Condensation/Evaporation on Arbitrarily Shaped Aerosols

Z. M. Smith and S. K. Loyalka

Nuclear Science and Engineering / Volume 176 / Number 2 / February 2014 / Pages 154-166

Technical Paper / dx.doi.org/10.13182/NSE12-107

Computational Evaluation of Neutron Multiplicity Measurements of Polyethylene-Reflected Plutonium Metal

E. C. Miller, J. K. Mattingly, S. D. Clarke, C. J. Solomon, and B. Dennis, A. Meldrum, and S. A. Pozzi

Nuclear Science and Engineering / Volume 176 / Number 2 / February 2014 / Pages 167-185

Technical Paper / dx.doi.org/10.13182/NSE12-53

The Development and Implementation of a One-Dimensional Sn Method in the 2D-1D Integral Transport Solution

M. Hursin, B. Collins, Y. Xu, and T. Downar

Nuclear Science and Engineering / Volume 176 / Number 2 / February 2014 / Pages 186-200

Technical Paper / dx.doi.org/10.13182/NSE12-4

Diffusion Acceleration Schemes for Self-Adjoint Angular Flux Formulation with a Void Treatment

Yaqi Wang, Hongbin Zhang, and Richard C. Martineau

Nuclear Science and Engineering / Volume 176 / Number 2 / February 2014 / Pages 201-225

Technical Paper / dx.doi.org/10.13182/NSE12-83

Multicycle Fuel Loading Pattern Optimization by Multiobjective Simulated Annealing Employing Adaptively Constrained Discontinuous Penalty Function

Tong Kyu Park, Han Gyu Joo, and Chang Hyo Kim

Nuclear Science and Engineering / Volume 176 / Number 2 / February 2014 / Pages 226-239

Technical Paper / dx.doi.org/10.13182/NSE12-41

A New Grid-Based Tomographic Method for Two-Phase Flow Measurements

Mayank Goswami, Anupam Saxena and Prabhat Munshi

Nuclear Science and Engineering / Volume 176 / Number 2 / February 2014 / Pages 240-253

Technical Paper / dx.doi.org/10.13182/NSE12-26

Number 3

Analyses of Material Effects on Steam Explosions in TROI FCI Tests

Ik Kyu Park, Jong Hwan Kim, and Seong Wan Hong

Nuclear Science and Engineering / Volume 176 / Number 3 / March 2014 / Pages 255-272

Technical Paper / dx.doi.org/10.13182/NSE13-16

A Coarse-Mesh Method for the Time-Dependent Transport Equation

Justin M. Pounders and Farzad Rahnema

Nuclear Science and Engineering / Volume 176 / Number 3 / March 2014 / Pages 273-291

Technical Paper / dx.doi.org/10.13182/NSE12-108

Consistent Spatial Homogenization in Transport Theory

Saam Yasseri and and Farzad Rahnema

Nuclear Science and Engineering / Volume 176 / Number 3 / March 2014 / Pages 292-311

Technical Paper / dx.doi.org/10.13182/NSE13-9

A Presentation of the OPTEX Reflector Model

Alain Hébert and Hadrien Leroyer

Nuclear Science and Engineering / Volume 176 / Number 3 / March 2014 / Pages 312-324

Technical Paper / dx.doi.org/10.13182/NSE13-26

Sensitivity Analysis and Data Assimilation in A Subcritical Plutonium Metal Benchmark

Richard T. Evans, John K. Mattingly, and Dan G. Cacuci

Nuclear Science and Engineering / Volume 176 / Number 3 / March 2014 / Pages 325-338

Technical Paper / dx.doi.org/10.13182/NSE13-24

Reducing Uncertainties via Predictive Modeling: FLICA4 Calibration Using BFBT Benchmarks

Dan G. Cacuci and Erkan Arslan

Nuclear Science and Engineering / Volume 176 / Number 3 / March 2014 / Pages 339-349

Technical Paper / dx.doi.org/10.13182/NSE13-31

Analytic Model for Dead Time Effect in Neutron Multiplicity Counting

C. Dubi, I. Israelashvili, and T. Ridnik

Nuclear Science and Engineering / Volume 176 / Number 3 / March 2014 / Pages 350-359

Technical Paper / dx.doi.org/10.13182/NSE13-2

Molecular Dynamics Simulation of Thermodynamic Properties in Uranium Dioxide

Xiangyu Wang, Bin Wu, Fei Gao, Xin Li, Xin Sun, Mohammed A. Khaleel, Ademola V. Akinlalu and Li Liu

Nuclear Science and Engineering / Volume 176 / Number 3 / March 2014 / Pages 360-369

Technical Paper / dx.doi.org/10.13182/NSE13-14

G4-STORK: A Monte Carlo Reactor Kinetics Simulation Code

Liam Russell, Adriaan Buijs, and Guy Jonkmans

Nuclear Science and Engineering / Volume 176 / Number 3 / March 2014 / Pages 370-375

Computer Code Abstract / dx.doi.org/10.13182/NSE13-8

 
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