Nuclear Science and Engineering -- ANS / Publications / Journals / Nuclear Science and Engineering

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Number 1

Table of Contents

Generation of Improved Isotopic Molybdenum Covariances from Elemental Cross-Section Data Using SAMMY
C. van der Hoeven, E. Schneider, L. Leal
Nuclear Science and Engineering | Volume 179 | Number 1 | January 2015 | Pages 1-21
Technical Paper | doi.org/10.13182/NSE13-78
Improved Monte Carlo Variance Reduction for Space and Energy Self-Shielding
S. C. Wilson, R. N. Slaybaugh
Nuclear Science and Engineering | Volume 179 | Number 1 | January 2015 | Pages 22-41
Technical Paper | doi.org/10.13182/NSE13-109
Preconditioned Multigroup GMRES Algorithms for the Variational Nodal Method
Yunzhao Li, E. E. Lewis, Micheal A. Smith, Hongchun Wu, Liangzhi Cao
Nuclear Science and Engineering | Volume 179 | Number 1 | January 2015 | Pages 42-58
Technical Paper | doi.org/10.13182/NSE13-103
Anisotropic Elastic Resonance Scattering Model for the Neutron Transport Equation
Mohamed Ouisloumen, Abderrafi M. Ougouag, Shadi Z. Ghrayeb
Nuclear Science and Engineering | Volume 179 | Number 1 | January 2015 | Pages 59-84
Technical Paper | doi.org/10.13182/NSE13-99
A Modal Expansion Equilibrium Cycle Perturbation Method for Optimizing Fast Reactors
Nicholas W. Touran, John C. Lee
Nuclear Science and Engineering | Volume 179 | Number 1 | January 2015 | Pages 85-103
Technical Paper | doi.org/10.13182/NSE13-85
Mathematical Modeling of Radioactive Contaminants in the Fukushima Environment
Akihiro Kitamura, Hiroshi Kurikami, Masaaki Yamaguchi, Yoshihiro Oda, Tatsuo Saito, Tomoko Kato, Tadafumi Niizato, Kazuki Iijima, Haruo Sato, Mikazu Yui, Masahiko Machida, Susumu Yamada, Mitsuhiro Itakura, Masahiko Okumura, Yasuo Onishi
Nuclear Science and Engineering | Volume 179 | Number 1 | January 2015 | Pages 104-118
Technical Paper | doi.org/10.13182/NSE13-89

Number 2

Table of Contents

A Novel Experimental Method for Validating Neutron Initiation Probability
Liu Xiaobo, Fan Xiaoqiang, Peng Xianjue, Du Jinfeng, Gao Hui
Nuclear Science and Engineering | Volume 179 | Number 2 | February 2015 | Pages 119-129
Technical Paper | doi.org/10.13182/NSE13-30
Uncertainty in the Fast Neutron Fluence in Function of the Fission Source and Its Burnup Dependence
Claude Mounier, Pietro Mosca
Nuclear Science and Engineering | Volume 179 | Number 2 | February 2015 | Pages 130-147
Technical Paper | doi.org/10.13182/NSE13-63
Lumping Techniques for DFEM S_N Transport in Slab Geometry
Peter G. Maginot, Jean C. Ragusa, Jim E. Morel
Nuclear Science and Engineering | Volume 179 | Number 2 | February 2015 | Pages 148-163
Technical Paper | doi.org/10.13182/NSE13-65
Calculation and Evaluation of Energy Spectra and Double-Differential Cross Sections for p+⁹⁰Zr Reactions up to 200 MeV
Juan Li, Zhengjun Zhang, Yinlu Han
Nuclear Science and Engineering | Volume 179 | Number 2 | February 2015 | Pages 164-185
Technical Paper | doi.org/10.13182/NSE13-84
Eigenvalue Implicit Sensitivity to Self-Shielding Calculations in Heterogeneous Geometries
M. Dion, G. Marleau
Nuclear Science and Engineering | Volume 179 | Number 2 | February 2015 | Pages 186-198
Technical Paper | doi.org/10.13182/NSE13-90
Lithium Adsorption on Magnetite, Lepidocrocite, and Maghemite at Elevated Temperatures
Liyan Qiu, Anthony P. Snaglewski
Nuclear Science and Engineering | Volume 179 | Number 2 | February 2015 | Pages 199-210
Technical Paper | doi.org/10.13182/NSE13-93
Critical Strains and Necking Phenomena for Steel Sheets Under Biaxial Loading During Accidents in Nuclear Power Plants
D. Ostermann, C. Krumb, R. Krieg
Nuclear Science and Engineering | Volume 179 | Number 2 | February 2015 | Pages 211-231
Technical Paper | doi.org/10.13182/NSE14-3

Number 3

Table of Contents
Letter to the Editor: New Magic Numbers and Their Significance (Roger A. Rydin)

An Improved Resonance Self-Shielding Calculation Method Based on Equivalence Theory
Qian Zhang, Hongchun Wu, Liangzhi Cao, Youqi Zheng
Nuclear Science and Engineering | Volume 179 | Number 3 | March 2015 | Pages 233-252
Technical Paper | doi.org/10.13182/NSE13-108
Stochastic Uncertainty Propagation in Monte Carlo Depletion Calculations
Quentin Newell, Charlotta Sanders
Nuclear Science and Engineering | Volume 179 | Number 3 | March 2015 | Pages 253-263
Technical Paper | doi.org/10.13182/NSE13-44
Lead Slowing-Down Spectrometry Analysis of Data from Measurements on Nuclear Fuel
Glen A. Warren, Kevin K. Anderson, Jonathan Kulisek, Yaron Danon, Adam Weltz, A. Gavron, Jason Harris, Trevor N. Stewart
Nuclear Science and Engineering | Volume 179 | Number 3 | March 2015 | Pages 264-273
Technical Paper | doi.org/10.13182/NSE13-71
One-Group Cross-Section Generation for Monte Carlo Burnup Codes: Multigroup Method Extension and Verification
D. Kotlyar, E. Fridman, E. Shwageraus
Nuclear Science and Engineering | Volume 179 | Number 3 | March 2015 | Pages 274-284
Technical Paper | doi.org/10.13182/NSE14-59
A New Method for the Doppler Broadening of the Solbrig's Kernel Using a Fourier Transform
G. Ferran, W. Haeck, M. Gonin
Nuclear Science and Engineering | Volume 179 | Number 3 | March 2015 | Pages 285-301
Technical Paper | doi.org/10.13182/NSE14-64
Validation of JEFF-3.1.1 Thermal and Epithermal Neutron-Induced Capture Cross Sections Through MELUSINE Experiment Analysis
David Bernard, Olivier Fabbris, Romain Gardet
Nuclear Science and Engineering | Volume 179 | Number 3 | March 2015 | Pages 302-312
Technical Paper | doi.org/10.13182/NSE13-104
Estimate of (n,p) Cross Section for Radionuclide ⁵⁵Fe Using EMPIRE and TALYS
Bhawna Pandey, P. M. Prajapati, S. Jakhar, C. V. S. Rao, T. K. Basu, B. K. Nayak, A. Saxena, S. V. Suryanarayana
Nuclear Science and Engineering | Volume 179 | Number 3 | March 2015 | Pages 313-320
Technical Paper | doi.org/10.13182/NSE14-26
Integrated Nondestructive Assay Systems to Estimate Plutonium in Spent Fuel Assemblies
T. Burr, H. Trellue, S. Tobin, A. Favalli, J. Dowell, V. Henzl, V. Mozin
Nuclear Science and Engineering | Volume 179 | Number 3 | March 2015 | Pages 321-332
Technical Paper | doi.org/10.13182/NSE14-38
A High-Order, Time-Dependent Response Matrix Method for Reactor Kinetics
Jeremy A. Roberts
Nuclear Science and Engineering | Volume 179 | Number 3 | March 2015 | Pages 333-341
Technical Note | doi.org/10.13182/NSE14-60
Bounding Parameters of a Theoretical Deep-Earth Uranium Fission Reactor
D. F. Hollenbach
Nuclear Science and Engineering | Volume 179 | Number 3 | March 2015 | Pages 342-351
Technical Note | doi.org/10.13182/NSE13-46

Number 4

Pressure Drop of Annular Flow Channel Electromagnetic Pump Examined Using Divided Flow Channel Model
Yosuke Hirata, Takatoshi Asada, Hideo Komita, Tetsu Suzuki, Rie Aizawa
Nuclear Science and Engineering | Volume 179 | Number 4 | April 2015 | Pages 355-363
Technical Paper | doi.org/10.13182/NSE13-82
Radiation Source Mapping with Bayesian Inverse Methods
Joshua M. Hykes, Yousry Y. Azmy
Nuclear Science and Engineering | Volume 179 | Number 4 | April 2015 | Pages 364-380
Technical Paper | doi.org/10.13182/NSE13-91
Impact of the Normalization Condition and Model Information on Evaluated Prompt Fission Neutron Spectra and Associated Uncertainties
D. Neudecker, R. Capote, D. L. Smith, T. Burr, P. Talou
Nuclear Science and Engineering | Volume 179 | Number 4 | April 2015 | Pages 381-397
Technical Paper | doi.org/10.13182/NSE14-6
A Statistical Approach for Experimental Cross-Section Covariance Estimation Via Shrinkage
S. Varet, P. Dossantos-Uzarralde, N. Vayatis
Nuclear Science and Engineering | Volume 179 | Number 4 | April 2015 | Pages 398-410
Technical Paper | doi.org/10.13182/NSE14-07
Computing Positive Semidefinite Multigroup Nuclear Data Covariances
Risto Vanhanen
Nuclear Science and Engineering | Volume 179 | Number 4 | April 2015 | Pages 411-422
Technical Paper | doi.org/10.13182/NSE14-75
Measurement and Covariance Analysis of Reaction Cross Sections for 58Ni(n,p)58Co Relative to Cross Section for Formation of Zr-97 Fission Product in Neutron-Induced Fission of Th-232 and U-238 at Effective Neutron Energies En = 5.89, 10.11, and 15.87 MeV
B. S. Shivashankar, S. Ganesan, H. Naik, S. V. Suryanarayana, N. Sreekumaran Nair, K. Manjunatha Prasad
Nuclear Science and Engineering | Volume 179 | Number 4 | April 2015 | Pages 423-433
Technical Paper | doi.org/10.13182/NSE14-19
Comparison of Neutronics-Depletion Coupling Schemes for Burnup Calculations
Aarno Isotalo, Ville Sahlberg
Nuclear Science and Engineering | Volume 179 | Number 4 | April 2015 | Pages 434-459
Technical Paper | doi.org/10.13182/NSE14-35
Analytical Green’s Function–Based Diffusion Monte Carlo with Transport Correction
Argala Srivastava, S. B. Degweker
Nuclear Science and Engineering | Volume 179 | Number 4 | April 2015 | Pages 460-476
Technical Paper | doi.org/10.13182/NSE14-42
An Assessment of the Fuel Pulverization Threshold During LOCA-Type Temperature Transients
J. A. Turnbull, S. K. Yagnik, M. Hirai, D. M. Staicu, C. T. Walker
Nuclear Science and Engineering | Volume 179 | Number 4 | April 2015 | Pages 477-485
Technical Paper | doi.org/10.13182/NSE14-20

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