American Nuclear Society
Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 174

Volume 174

Number 1 | Number 2 | Number 3

Number 1

Time Interval Distributions and the Rossi Correlation Function

M. Prasad, N. Snyderman, J. Verbeke, R. Wurtz

Nuclear Science and Engineering / Volume 174 / Number 1 / May 2013 / Pages 1-29

Technical Paper / dx.doi.org/10.13182/NSE11-87

Kernel Density Estimation Method for Monte Carlo Point Detector and Surface Crossing Flux Tallies

Kaushik Banerjee, William R. Martin

Nuclear Science and Engineering / Volume 174 / Number 1 / May 2013 / Pages 30-45

Technical Paper / dx.doi.org/10.13182/NSE11-94

Analysis of KROTOS Steam Explosion Experiments Using the Improved Fuel-Coolant-Interaction Code TEXAS-VI

R. H. Chen, M. L. Corradini, G. H. Su, S. Z. Qiu

Nuclear Science and Engineering / Volume 174 / Number 1 / May 2013 / Pages 46-59

Technical Paper / dx.doi.org/10.13182/NSE12-22

Simulation of Unsteady Flow Through a String of CANDU Fuel Bundles in a Pressure Tube

A. Bhattacharya, S. D. Yu

Nuclear Science and Engineering / Volume 174 / Number 1 / May 2013 / Pages 60-78

Technical Paper / dx.doi.org/10.13182/NSE12-31

Quadratic Depletion Method for Gadolinium Isotopes in CASMO-5

Deokjung Lee, Joel Rhodes, Kord Smith

Nuclear Science and Engineering / Volume 174 / Number 1 / May 2013 / Pages 79-86

Technical Paper / dx.doi.org/10.13182/NSE12-20

A Novel, Robust Control Methodology Application to Nuclear Reactors

Hassan M. Emara, Adel A. Hanafy, Magdy M. Zaky Abdelaal, Sayed Elaraby

Nuclear Science and Engineering / Volume 174 / Number 1 / May 2013 / Pages 87-95

Technical Paper / dx.doi.org/10.13182/NSE12-8

Instrumentation for Sodium-Cooled Fast Breeder Reactors

Govind Kumar Mishra, M. Sakthivel, S. L. N. Swamy, K. Madhusoodanan

Nuclear Science and Engineering / Volume 174 / Number 1 / May 2013 / Pages 96-102

Technical Note / dx.doi.org/10.13182/NSE10-74

Monte Carlo Investigation on the Average Prompt Neutron Multiplicity as a Function of the Total Kinetic Energy and Mass of the Fragments from 252Cf Spontaneous Fission

David Regnier, Olivier Litaize, Olivier Serot

Nuclear Science and Engineering / Volume 174 / Number 1 / May 2013 / Pages 103-108

Technical Note / dx.doi.org/10.13182/NSE12-12

Number 2

Multicell Correction Method for Treatment of Heterogeneities in Full-Core Calculation of CANDU-Type Reactors

Wei Shen, Dimitar Altiparmakov

Nuclear Science and Engineering / Volume 174 / Number 2 / June 2013 / Pages 109-134

Technical Paper / dx.doi.org/10.13182/NSE12-42

Neutronic Analysis of the Oregon State TRIGA Reactor in Support of Conversion from HEU Fuel to LEU Fuel

M. R. Hartman, S. T. Keller, S. R. Reese, B. Robinson, J. Stevens, J. E. Matos, W. R. Marcum, T. S. Palmer, B. G. Woods

Nuclear Science and Engineering / Volume 174 / Number 2 / June 2013 / Pages 135-149

Technical Paper / dx.doi.org/10.13182/NSE12-5

Multilevel NDA Methods for Solving Multigroup Eigenvalue Neutron Transport Problems

Dmitriy Y. Anistratov

Nuclear Science and Engineering / Volume 174 / Number 2 / June 2013 / Pages 150-162

Technical Paper / dx.doi.org/10.13182/NSE12-28

Unstructured Triangular Nodal-SP3 Method Based on an Exponential Function Expansion

Yunzhao Li, Hongchun Wu, Liangzhi Cao

Nuclear Science and Engineering / Volume 174 / Number 2 / June 2013 / Pages 163-171

Technical Paper / dx.doi.org/10.13182/NSE11-111

Stochastic Eigenvalues in Multiplying Systems

M. M. R. Williams

Nuclear Science and Engineering / Volume 174 / Number 2 / June 2013 / Pages 172-178

Technical Paper / dx.doi.org/10.13182/NSE12-45

Predicted Water Chemistry in the Primary Coolant Circuit of a Supercritical Water Reactor

Mei-Ya Wang, Tsung-Kuang Yeh, Hong-Ming Liu, Min Lee

Nuclear Science and Engineering / Volume 174 / Number 2 / June 2013 / Pages 179-187

Technical Paper / dx.doi.org/10.13182/NSE12-16

Quasi-Differential Neutron Scattering in Zirconium from 0.5 to 20 MeV

D. P. Barry, G. Leinweber, R. C. Block, T. J. Donovan, Y. Danon, F. J. Saglime, A. M. Daskalakis, M. J. Rapp, R. M. Bahran

Nuclear Science and Engineering / Volume 174 / Number 2 / June 2013 / Pages 188-201

Technical Paper / dx.doi.org/10.13182/NSE12-1

Measurements of Isomeric Cross Sections for (n,) Reaction on 144Sm Isotope for Neutrons Around 14 MeV

Iskender Atilla Reyhancan, Ayse Durusoy

Nuclear Science and Engineering / Volume 174 / Number 2 / June 2013 / Pages 202-207

Technical Paper / dx.doi.org/10.13182/NSE11-96

Number 3

A Cellwise Block-Gauss-Seidel Iterative Method for Multigroup SN Transport on a Hybrid Parallel Computer Architecture

Massimiliano Rosa, James S. Warsa, Michael Perks

Nuclear Science and Engineering / Volume 174 / Number 3 / July 2013 / Pages 209-226

Technical Paper / dx.doi.org/10.13182/NSE12-57

Adjoint-Based k-Eigenvalue Sensitivity Coefficients to Nuclear Data Using Continuous-Energy Monte Carlo

Brian C. Kiedrowski, Forrest B. Brown

Nuclear Science and Engineering / Volume 174 / Number 3 / July 2013 / Pages 227-244

Technical Paper / dx.doi.org/10.13182/NSE12-46

Diffusion Theory-Based Analog Monte Carlo for Simulating Noise Experiments in Subcritical Systems

Y. S. Rana, Arun Singh, S. B. Degweker

Nuclear Science and Engineering / Volume 174 / Number 3 / July 2013 / Pages 245-263

Technical Paper / dx.doi.org/10.13182/NSE11-117

Prediction of Pebble Motion in Pebble-Bed Reactors Using Monte Carlo Molecular Dynamics Simulation

Kyoung O. Lee, Robin P. Gardner

Nuclear Science and Engineering / Volume 174 / Number 3 / July 2013 / Pages 264-285

Technical Paper / dx.doi.org/10.13182/NSE12-23

Hybrid Monte Carlo-CMFD Methods for Accelerating Fission Source Convergence

Emily R. Wolters, Edward W. Larsen, William R. Martin

Nuclear Science and Engineering / Volume 174 / Number 3 / July 2013 / Pages 286-299

Technical Paper / dx.doi.org/10.13182/NSE12-72

Impact of Dynamic Condensation of Energy Groups on Convergence Behavior of One-Node CMFD Method for Neutron Diffusion Problem

Deokjung Lee

Nuclear Science and Engineering / Volume 174 / Number 3 / July 2013 / Pages 300-317

Technical Paper / dx.doi.org/10.13182/NSE12-27

Modeling of Nonuniform Density Distributions in the Serpent 2 Monte Carlo Code

Jaakko Leppänen

Nuclear Science and Engineering / Volume 174 / Number 3 / July 2013 / Pages 318-325

Technical Paper / dx.doi.org/10.13182/NSE12-54

 
Questions or comments about the site? Contact the ANS Webmaster.
advertisement