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Volume 179

Number 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

 
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