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Home / Publications / Journals / Nuclear Science and Engineering / Volume 165

Volume 165

Number 1 | Number 2 | Number 3

Number 1

On the Evaluation of Discrepant Scientific Data with Unrecognized Errors

Dan G. Cacuci, Mihaela Ionescu-Bujor

Nuclear Science and Engineering / Volume 165 / Number 1 / May 2010 / Pages 1-17

Technical Paper

Best-Estimate Model Calibration and Prediction Through Experimental Data Assimilation - I: Mathematical Framework

Dan G. Cacuci, Mihaela Ionescu-Bujor

Nuclear Science and Engineering / Volume 165 / Number 1 / May 2010 / Pages 18-44

Technical Paper

Best-Estimate Model Calibration and Prediction Through Experimental Data Assimilation - II: Application to a Blowdown Benchmark Experiment

Alessandro Petruzzi, Dan G. Cacuci, Francesco D'Auria

Nuclear Science and Engineering / Volume 165 / Number 1 / May 2010 / Pages 45-100

Technical Paper

Scaled and Full-Size Three-Loop Reactor Vessel Simulation for Boron Dilution Studies Using Computational Fluid Dynamics

T. V. Dury, M. T. Dhotre

Nuclear Science and Engineering / Volume 165 / Number 1 / May 2010 / Pages 101-116

Technical Paper

The 235U(n,f) Prompt Fission Neutron Spectrum at 100 K Input Neutron Energy

N. Kornilov, F.-J. Hambsch, I. Fabry, S. Oberstedt, T. Belgya, Z. Kis, L. Szentmiklosi, S. Simakov

Nuclear Science and Engineering / Volume 165 / Number 1 / May 2010 / Pages 117-127

Technical Paper

Comments on “Numerical Stability of Existing Monte Carlo Burnup Codes in Cycle Calculations of Critical Reactors”

Gray S. Chang

Nuclear Science and Engineering / Volume 165 / Number 1 / May 2010 / Pages 128-130

Letter to the Editor

Reply to “Comments on ‘Numerical Stability of Existing Monte Carlo Burnup Codes in Cycle Calculations of Critical Reactors’”

Jan Dufek

Nuclear Science and Engineering / Volume 165 / Number 1 / May 2010 / Pages 130-131

Letter to the Editor

Number 2

Nonlinear Weighted Flux Methods for Particle Transport Problems in Two-Dimensional Cartesian Geometry

Loren Roberts, Dmitriy Y. Anistratov

Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 133-148

Technical Paper

Asymptotic Diffusion-Limit Accuracy of Sn Angular Differencing Schemes

Teresa S. Bailey, Jim E. Morel, Jae H. Chang

Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 149-169

Technical Paper

Adaptive Three-Dimensional Monte Carlo Functional-Expansion Tallies

Brian C. Franke, Ronald P. Kensek

Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 170-179

Technical Paper

Transient Two-Dimensional Hydrodynamic Experiments

Aya Diab, Michael Corradini

Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 180-199

Technical Paper

Reanalysis of Recent Neutron Diffusion and Transmission Measurements in Nuclear Graphite

C. R. Gould, A. I. Hawari, E. I. Sharapov

Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 200-209

Technical Paper

The Impact of Power Coastdown Operations on the Water Chemistry and Corrosion in Boiling Water Reactors

Tsung-Kuang Yeh, Mei-Ya Wang

Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 210-223

Technical Paper

Cross Sections for 239Pu(n,f) and 241Pu(n,f) in the Range En = 0.01 eV to 200 MeV

F. Tovesson, T. S. Hill

Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 224-231

Technical Paper

Recent Progress in the Design of a Tomographic Device for Measurements of the Three-Dimensional Pin-Power Distribution in Irradiated Nuclear Fuel Assemblies

Tobias Lundqvist Saleh, Staffan Jacobsson Svärd, Ane Håkansson, A. Bäcklin

Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 232-239

Technical Note

A Study of Photon Interaction and Photon Energy Absorption Effective Atomic Numbers for Some Amino Acids

Tejbir Singh, Updesh Kaur, Shivali Tandon, Parjit S. Singh

Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 240-244

Technical Note

Number 3

Automated Design and Optimization of Pebble-Bed Reactor Cores

H. D. Gougar, A. M. Ougouag, W. K. Terry, K. N. Ivanov

Nuclear Science and Engineering / Volume 165 / Number 3 / July 2010 / Pages 245-269

Technical Paper

Spatial Corrections for Pulsed-Neutron Reactivity Measurements

Yan Cao, John C. Lee

Nuclear Science and Engineering / Volume 165 / Number 3 / July 2010 / Pages 270-282

Technical Paper

Exact Regional Monte Carlo Weight Cancellation for Second Eigenfunction Calculations

Thomas E. Booth, James E. Gubernatis

Nuclear Science and Engineering / Volume 165 / Number 3 / July 2010 / Pages 283-291

Technical Paper

A Transport Acceleration Scheme for Multigroup Discrete Ordinates with Upscattering

Thomas M. Evans, Kevin T. Clarno, Jim E. Morel

Nuclear Science and Engineering / Volume 165 / Number 3 / July 2010 / Pages 292-304

Technical Paper

Goal-Oriented h-Adaptivity for the Multigroup SPN Equations

Bruno Turcksin, Jean C. Ragusa, Wolfgang Bangerth

Nuclear Science and Engineering / Volume 165 / Number 3 / July 2010 / Pages 305-319

Technical Paper

Extension of Differential Operator Method to Inhomogeneous Problems with Internal and External Neutron Sources

Kirill Fedorovich Raskach

Nuclear Science and Engineering / Volume 165 / Number 3 / July 2010 / Pages 320-330

Technical Paper

The Newton-Krylov Method Applied to Negative-Flux Fixup in SN Transport Calculations

Erin D. Fichtl, James S. Warsa, Jeffery D. Densmore

Nuclear Science and Engineering / Volume 165 / Number 3 / July 2010 / Pages 331-341

Technical Paper

 
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