ANS / Publications / Journals / Nuclear Science and Engineering

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE13-89

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE14-3

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE13-46

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE14-20