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Volume 186

Number 1 | Number 2 | Number 3

Number 1

GENESIS: A Three-Dimensional Heterogeneous Transport Solver Based on the Legendre Polynomial Expansion of Angular Flux Method

Akio Yamamoto, Akinori Giho, Yuki Kato, Tomohiro Endo

Nuclear Science and Engineering / Volume 186 / Number 1 / April 2017 / Pages 1-22

Technical Paper / dx.doi.org/10.1080/00295639.2016.1273002

Fourier Convergence Analysis of the Infinite Homogenous Multigroup Time-Dependent Boltzmann Transport Equation Using Discrete Ordinates Formulation

Ang Zhu, Yunlin Xu, Thomas Downar

Nuclear Science and Engineering / Volume 186 / Number 1 / April 2017 / Pages 23-37

Technical Paper / dx.doi.org/10.1080/00295639.2016.1272387

The Effects of Oxidizing Species on Cobalt Buildup in a BWR Environment

Motomasa Fuse, Naoshi Usui, Nobuyuki Ohta, Yoshiteru Sato, Ryosuke Shimizu, Hideyuki Hosokawa, Tsuyoshi Ito, Yoichi Wada

Nuclear Science and Engineering / Volume 186 / Number 1 / April 2017 / Pages 38-47

Technical Paper / dx.doi.org/10.1080/00295639.2016.1272385

Evaluation of Uranium-Based Fuels Augmented by Low Levels of Thorium for Near-Term Implementation in Pressure Tube Heavy Water Reactors

Ashlea V. Colton, Blair P. Bromley, Daniel Wojtaszek, Clifford Dugal

Nuclear Science and Engineering / Volume 186 / Number 1 / April 2017 / Pages 48-65

Technical Paper / dx.doi.org/10.1080/00295639.2016.1273021

Illuminating Fuel Cycle Decision Drivers Using a Decision Analysis Framework

Lara M. Pierpoint

Nuclear Science and Engineering / Volume 186 / Number 1 / April 2017 / Pages 66-82

Technical Paper / dx.doi.org/10.1080/00295639.2016.1272386

Facility Deployment Decisions Through Warp Optimization of Regressed Gaussian Processes

Anthony Michael Scopatz

Nuclear Science and Engineering / Volume 186 / Number 1 / April 2017 / Pages 83-97

Technical Paper / dx.doi.org/10.1080/00295639.2016.1272384

Development of Bounding Burnup Axial Profiles for WWER-440 Spent Fuel Pool Burnup Credit Analysis

S. Bznuni, N. Baghdasaryan, A. Amirjanyan, G. Nazaryan, P. Kohut, J. Ramsey

Nuclear Science and Engineering / Volume 186 / Number 1 / April 2017 / Pages 98-102

Technical Paper / dx.doi.org/10.1080/00295639.2016.1273012

Number 2

A Computationally Viable Version of the PN Method for Spheres

R. D. M. Garcia, C. E. Siewert, J. R. Thomas Jr.

Nuclear Science and Engineering / Volume 186 / Number 2 / May 2017 / Pages 103-119

Technical Paper / dx.doi.org/10.1080/00295639.2016.1273627

A Variational Nodal Approach to 2D/1D Pin Resolved Neutron Transport for Pressurized Water Reactors

Tengfei Zhang, E. E. Lewis, M. A. Smith, W. S. Yang, Hongchun Wu

Nuclear Science and Engineering / Volume 186 / Number 2 / May 2017 / Pages 120-133

Technical Paper / dx.doi.org/10.1080/00295639.2016.1273023

Evaluation of Pin-Cell Homogenization Techniques for PWR Pin-by-Pin Calculation

Bin Zhang, Hongchun Wu, Yunzhao Li, Liangzhi Cao, Wei Shen

Nuclear Science and Engineering / Volume 186 / Number 2 / May 2017 / Pages 134-146

Technical Paper / dx.doi.org/10.1080/00295639.2016.1273018

A New Method for Generating Probability Tables in the Unresolved Resonance Region

Andrew Holcomb, Luiz Leal, Farzad Rahnema, Dorothea Wiarda

Nuclear Science and Engineering / Volume 186 / Number 2 / May 2017 / Pages 147-155

Technical Paper / dx.doi.org/10.1080/00295639.2016.1273632

Calculation and Evaluation for the n+51V Reaction

Hairui Guo, Yongli Xu, Yinlu Han, Qingbiao Shen, Tao Ye, Weili Sun

Nuclear Science and Engineering / Volume 186 / Number 2 / May 2017 / Pages 156-167

Technical Paper / dx.doi.org/10.1080/00295639.2016.1273008

A Simple and Practical Correction Technique for Reactivity Worth of Short-Sized Samples Measured by Critical-Water-Level Method

Yasunori Kitamura, Masahiro Fukushima

Nuclear Science and Engineering / Volume 186 / Number 2 / May 2017 / Pages 168-179

Technical Paper / dx.doi.org/10.1080/00295639.2016.1273017

Evaluation of Early Hydrogen Water Chemistry on Corrosion Mitigation in Boiling Water Reactors

Mei-Ya Wang, Tsung-Kuang Yeh

Nuclear Science and Engineering / Volume 186 / Number 2 / May 2017 / Pages 180-189

Technical Paper / dx.doi.org/10.1080/00295639.2016.1273014

What Is the Real PFNS of 235U at Thermal Point?

N. V. Kornilov

Nuclear Science and Engineering / Volume 186 / Number 2 / May 2017 / Pages 190-198

Technical Paper / dx.doi.org/10.1080/00295639.2016.1273625

Number 3

Inverse Predictive Modeling of Radiation Transport Through Optically Thick Media in the Presence of Counting Uncertainties

Dan Gabriel Cacuci

Nuclear Science and Engineering / Volume 186 / Number 3 / June 2017 / Pages 199-223

Technical Paper / dx.doi.org/10.1080/00295639.2017.1305244

Theoretical Convergence Rate Lower Bounds for Variants of Coarse Mesh Finite Difference to Accelerate Neutron Transport Calculations

Ang Zhu, Brendan Kochunas, Yunlin Xu, Michael Jarrett, Edward Larsen, Thomas Downar

Nuclear Science and Engineering / Volume 186 / Number 3 / June 2017 / Pages 224-238

Technical Paper / dx.doi.org/10.1080/00295639.2017.1293408

A Neutron Transport Characteristics Method for 3D Axially Extruded Geometries Coupled with a Fine Group Self-Shielding Environment

S. Santandrea, D. Sciannandrone, R. Sanchez, L. Mao, L. Graziano

Nuclear Science and Engineering / Volume 186 / Number 3 / June 2017 / Pages 239-276

Technical Paper / dx.doi.org/10.1080/00295639.2016.1273634

Neutron Time Interval Distributions with Background Neutrons

Manoj Prasad, Neal Snyderman, Sean Walston

Nuclear Science and Engineering / Volume 186 / Number 3 / June 2017 / Pages 277-292

Technical Paper / dx.doi.org/10.1080/00295639.2016.1273620

A Simple Iterative Method for Compensating the Response Delay of a Self-Powered Neutron Detector

Qingmin Zhang, Zhigang Hu, Bangjie Deng, Mengxuan Xu, Yuhang Guo

Nuclear Science and Engineering / Volume 186 / Number 3 / June 2017 / Pages 293-302

Technical Paper / dx.doi.org/10.1080/00295639.2016.1273619

 
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