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Volume 163

Number 1 | Number 2 | Number 3

Number 1

The 10B(n,0)7Li and 10B(n,1)7Li Alpha-Particle Angular Distributions for En < 1 MeV

F.-J. Hambsch, I. Ruskov

Nuclear Science and Engineering / Volume 163 / Number 1 / September 2009 / Pages 1-16

Technical Paper / dx.doi.org/10.13182/NSE09-1

Impact of New Gadolinium Cross Sections on Reaction Rate Distributions in 10 × 10 BWR Assemblies

G. Perret, M. F. Murphy, F. Jatuff, J-Ch. Sublet, O. Bouland, R. Chawla

Nuclear Science and Engineering / Volume 163 / Number 1 / September 2009 / Pages 17-25

Technical Paper / dx.doi.org/10.13182/NSE08-55

Isotopic Signatures of Weapon-Grade Plutonium from Dedicated Natural Uranium-Fueled Production Reactors and Their Relevance for Nuclear Forensic Analysis

Alexander Glaser

Nuclear Science and Engineering / Volume 163 / Number 1 / September 2009 / Pages 26-33

Technical Paper / dx.doi.org/10.13182/NSE163-26

A Wavelet-Based Finite Element Method for the Self-Shielding Issue in Neutron Transport

R. Le Tellier, D. Fournier, J. M. Ruggieri

Nuclear Science and Engineering / Volume 163 / Number 1 / September 2009 / Pages 34-55

Technical Paper / dx.doi.org/10.13182/NSE163-34

On the Convergence of DGFEM Applied to the Discrete Ordinates Transport Equation for Structured and Unstructured Triangular Meshes

Yaqi Wang, Jean C. Ragusa

Nuclear Science and Engineering / Volume 163 / Number 1 / September 2009 / Pages 56-72

Technical Paper / dx.doi.org/10.13182/NSE08-72

Surface and Volume Integrals of Uncollided Adjoint Fluxes and Forward-Adjoint Flux Products

Jeffrey A. Favorite, Keith C. Bledsoe, David I. Ketcheson

Nuclear Science and Engineering / Volume 163 / Number 1 / September 2009 / Pages 73-84

Technical Paper / dx.doi.org/10.13182/NSE163-73

Spreading of Collimated Particle Beams Within a Generalized Fokker-Planck Diffusion Description

R. Nyqvist, D. Anderson, M. Lisak

Nuclear Science and Engineering / Volume 163 / Number 1 / September 2009 / Pages 85-90

Technical Note / dx.doi.org/10.13182/NSE163-85

Number 2

Step-Refined On-the-Fly Convergence Diagnostics of Monte Carlo Fission Source Distribution

Taro Ueki

Nuclear Science and Engineering / Volume 163 / Number 2 / October 2009 / Pages 99-117

Technical Paper / dx.doi.org/10.13182/NSE163-99

Development of a Three-Dimensional Time-Dependent Calculation Scheme for Molten Salt Reactors and Validation of the Measurement Data of the Molten Salt Reactor Experiment

J. Kópházi, D. Lathouwers, J. L. Kloosterman

Nuclear Science and Engineering / Volume 163 / Number 2 / October 2009 / Pages 118-131

Technical Paper / dx.doi.org/10.13182/NSE163-118

Multiphysics Analysis of Spherical Fast Burst Reactors

Samet Y. Kadioglu, Dana A. Knoll, Cassiano de Oliveira

Nuclear Science and Engineering / Volume 163 / Number 2 / October 2009 / Pages 132-143

Technical Paper / dx.doi.org/10.13182/NSE09-07

Projected Predictor-Corrector Method for Lattice Physics Burnup Calculations

Akio Yamamoto, Masahiro Tatsumi, Naoki Sugimura

Nuclear Science and Engineering / Volume 163 / Number 2 / October 2009 / Pages 144-151

Technical Paper / dx.doi.org/10.13182/NSE08-80

A Three-Scale Expansion Solution for a Time-Dependent P1 Neutron Transport Problem with External Source

B. Merk, F. P. Weiß

Nuclear Science and Engineering / Volume 163 / Number 2 / October 2009 / Pages 152-174

Technical Paper / dx.doi.org/10.13182/NSE163-152

Measurement of 67Zn(n,p)67Cu, 92Mo(n,p)92mNb, and 98Mo(n,)99Mo Reaction Cross Sections at Incident Neutron Energies of En = 1.6 and 3.7 MeV

Megha Bhike, A. Saxena, B. J. Roy, R. K. Choudhury, S. Kailas, S. Ganesan

Nuclear Science and Engineering / Volume 163 / Number 2 / October 2009 / Pages 175-182

Technical Paper / dx.doi.org/10.13182/NSE163-175

Optimization of Spent Nuclear Fuel Filling in Canisters for Deep Repository

Gasper Zerovnik, Luka Snoj, Matjaz Ravnik

Nuclear Science and Engineering / Volume 163 / Number 2 / October 2009 / Pages 183-190

Technical Paper / dx.doi.org/10.13182/NSE163-183

Number 3

Adaptive Partial-Current Discrete Ordinates Radiation Transport with Distribution Iteration: An Alternative to Source Iteration

Kirk Mathews, James Dishaw, Nicholas Wager, Nicholas Prins

Nuclear Science and Engineering / Volume 163 / Number 3 / November 2009 / Pages 191-214

Technical Paper / dx.doi.org/10.13182/NSE163-191

Actinide Transmutation in PWRs Using CONFU Assemblies

M. Visosky, Y. Shatilla, P. Hejzlar, M. S. Kazimi

Nuclear Science and Engineering / Volume 163 / Number 3 / November 2009 / Pages 215-242

Technical Paper / dx.doi.org/10.13182/NSE193-215

On the Diffusion Coefficients for Reactor Physics Applications

Justin M. Pounders, Farzad Rahnema

Nuclear Science and Engineering / Volume 163 / Number 3 / November 2009 / Pages 243-262

Technical Paper / dx.doi.org/10.13182/NSE163-243

Use of a New Boundary Condition in Computational Neutron Transport

R. S. Modak, Anurag Gupta

Nuclear Science and Engineering / Volume 163 / Number 3 / November 2009 / Pages 263-271

Technical Paper / dx.doi.org/10.13182/NSE163-263

Double-Differential Neutron Emission Cross-Section Measurements of 6Li and 7Li at Incident Neutron Energies of 8.17 and 10.27 MeV

Guochang Chen, Xichao Ruan, Zuying Zhou, Jingshang Zhang, Bujia Qi, Xia Li, Hanxiong Huang, Hongqing Tang, Qiping Zhong, Jing Jiang, Biao Xin, Jie Bao, Lin Chen

Nuclear Science and Engineering / Volume 163 / Number 3 / November 2009 / Pages 272-284

Technical Paper / dx.doi.org/10.13182/NSE163-272

Subcritical Noise Measurements with a Nickel-Reflected Plutonium Sphere

Jesson D. Hutchinson, John D. Bess

Nuclear Science and Engineering / Volume 163 / Number 3 / November 2009 / Pages 285-290

Technical Paper / dx.doi.org/10.13182/NSE163-285

 
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