ANS / Publications / Journals / Nuclear Science and Engineering

Comparison of Spatial Discretization Methods for Solving the S_N Equations Using a Three-Dimensional Method of Manufactured Solutions Benchmark Suite with Escalating Order of Nonsmoothness

Sebastian Schunert, Yousry Azmy

Nuclear Science and Engineering / Volume 180 / Number 1 / May 2015 / Pages 1-29

Technical Paper / dx.doi.org/10.13182/NSE14-77

A New Equivalence Theory Method for Treating Doubly Heterogeneous Fuel—I: Theory

Mark L. Williams, Sooyoung Choi, Deokjung Lee

Nuclear Science and Engineering / Volume 180 / Number 1 / May 2015 / Pages 30-40

Technical Paper / dx.doi.org/10.13182/NSE14-68

A New Equivalence Theory Method for Treating Doubly Heterogeneous Fuel—II: Verifications

Sooyoung Choi, Chidong Kong, Deokjung Lee, Mark L. Williams

Nuclear Science and Engineering / Volume 180 / Number 1 / May 2015 / Pages 41-57

Technical Paper / dx.doi.org/10.13182/NSE14-72

Robust Statistical Error Estimation of Local Power Tallies in Monte Carlo Calculation of Light Water Reactor

Taro Ueki

Nuclear Science and Engineering / Volume 180 / Number 1 / May 2015 / Pages 58-68

Technical Paper / dx.doi.org/10.13182/NSE14-54

A Hybrid Monte Carlo/Method-of-Characteristics Method for Efficient Neutron Transport Analysis

Hyunsuk Lee, Sooyoung Choi, Deokjung Lee

Nuclear Science and Engineering / Volume 180 / Number 1 / May 2015 / Pages 69-85

Technical Paper / dx.doi.org/10.13182/NSE13-102

Neutron Capture Measurements and Resonance Parameters of Gadolinium

Y.-R. Kang, M. W. Lee, G. N. Kim, T.-I. Ro, Y. Danon, D. Williams, G. Leinweber, R. C. Block, D. P. Barry, M. J. Rapp

Nuclear Science and Engineering / Volume 180 / Number 1 / May 2015 / Pages 86-116

Technical Paper / dx.doi.org/10.13182/NSE14-80

Plasma Temperature Inference From Deuterium-Tritium/Deuterium-Deuterium Neutron Discrimination

J. I. Katz

Nuclear Science and Engineering / Volume 180 / Number 1 / May 2015 / Pages 117-122

Technical Note / dx.doi.org/10.13182/NSE14-81

A New Molybdenum Production Element for Implementation in TRIGA Reactors: Thermal-Hydraulic Characterization

W. R. Marcum, P. Y. Byfield, S. R. Reese

Nuclear Science and Engineering / Volume 180 / Number 2 / June 2015 / Pages 123-140

Technical Paper / dx.doi.org/10.13182/NSE14-93

Study of Critical Heat Flux in Natural Convection–Cooled TRIGA Reactors with Single Annulus and Rod Bundle Geometries

Jun Yang, Michael Scott Greenwood, Matthew De Angelis, Michael Avery, Mark Anderson, Michael Corradini, James Matos, Floyd Dunn, Earl Feldman

Nuclear Science and Engineering / Volume 180 / Number 2 / June 2015 / Pages 141-153

Technical Paper / dx.doi.org/10.13182/NSE14-45

Global Control of H-Infinity Multimodel System with Gap Metric and Self-Stability for Load-Following Nuclear Reactor Core

Gang Li

Nuclear Science and Engineering / Volume 180 / Number 2 / June 2015 / Pages 154-171

Technical Paper / dx.doi.org/10.13182/NSE13-87

Determination of Turbulent Mixing Rate for Single-Phase Flow in Simulated Subchannels of a Natural-Circulation Pressure Tube–Type BWR

M. P. Sharma, A. K. Nayak

Nuclear Science and Engineering / Volume 180 / Number 2 / June 2015 / Pages 172-181

Technical Paper / dx.doi.org/10.13182/NSE14-102

Validation of the Legendre Expansion of the Collision Law for Light Water Reactor Calculations

Ansar Calloo, Jean-François Vidal, Romain Le Tellier, Gérald Rimpault

Nuclear Science and Engineering / Volume 180 / Number 2 / June 2015 / Pages 182-198

Technical Paper / dx.doi.org/10.13182/NSE14-57

Monte Carlo Fission Matrix Acceleration Method with Limited Inner Iteration

Liujun Pan, Ruihong Wang, Song Jiang

Nuclear Science and Engineering / Volume 180 / Number 2 / June 2015 / Pages 199-208

Technical Paper / dx.doi.org/10.13182/NSE14-73

Temperature Majorant Cross Sections in Monte Carlo Neutron Tracking

Tuomas Viitanen, Jaakko Leppänen

Nuclear Science and Engineering / Volume 180 / Number 2 / June 2015 / Pages 209-223

Technical Paper / dx.doi.org/10.13182/NSE14-46

The Infinite Medium Green’s Function of Monoenergetic Neutron Transport Theory via Fourier Transform

B. D. Ganapol

Nuclear Science and Engineering / Volume 180 / Number 2 / June 2015 / Pages 224-246

Technical Paper / dx.doi.org/10.13182/NSE14-55

A Full-Core Resonance Self-Shielding Method Using a Continuous-Energy Quasi–One-Dimensional Slowing-Down Solution that Accounts for Temperature-Dependent Fuel Subregions and Resonance Interference

Yuxuan Liu, William Martin, Mark Williams, Kang-Seog Kim

Nuclear Science and Engineering / Volume 180 / Number 3 / July 2015 / Pages 247-272

Technical Paper / dx.doi.org/10.13182/NSE14-65

Lagrange Discrete Ordinates: A New Angular Discretization for the Three-Dimensional Linear Boltzmann Equation

Cory D. Ahrens

Nuclear Science and Engineering / Volume 180 / Number 3 / July 2015 / Pages 273-285

Technical Paper / dx.doi.org/10.13182/NSE14-76

Comparison of Neutronics-Depletion Coupling Schemes for Burnup Calculations—Continued Study

Aarno Isotalo

Nuclear Science and Engineering / Volume 180 / Number 3 / July 2015 / Pages 286-300

Technical Paper / dx.doi.org/10.13182/NSE14-92

Effects of Bubble Injection on Heat Transfer from a Volumetrically Heated Water Pool

Geoffrey R. Bull, Jason O. Oakley, Michael L. Corradini

Nuclear Science and Engineering / Volume 180 / Number 3 / July 2015 / Pages 301-311

Technical Paper / dx.doi.org/10.13182/NSE14-79

The Magnitude of Combined Physical and Chemical Explosions: A Mechanism for a Steam-Metal Chemical Explosion with Highly Reactive Metals

Robert E. Henry, Michael Epstein, Hans K. Fauske

Nuclear Science and Engineering / Volume 180 / Number 3 / July 2015 / Pages 312-334

Technical Paper / dx.doi.org/10.13182/NSE14-90

The Effectiveness of Hydrogen Water Chemistry on Corrosion Mitigation in an Advanced Boiling Water Reactor

Mei-Ya Wang, Tsung-Kuang Yeh

Nuclear Science and Engineering / Volume 180 / Number 3 / July 2015 / Pages 335-340

Technical Paper / dx.doi.org/10.13182/NSE14-97

Neutron Interactions with ³He Revisited—III: Neutron Cross Sections Between 24 and 30 MeV

M. Drosg

Nuclear Science and Engineering / Volume 180 / Number 3 / July 2015 / Pages 341-344

Technical Note / dx.doi.org/10.13182/NSE14-96

Ambiguities in the Sensitivity and Uncertainty Analysis of Reactor Physics Problems Involving Constrained Quantities

Zoltán Perkó, Danny Lathouwers, Jan Leen Kloosterman, Tim H. J. J. van der Hagen

Nuclear Science and Engineering / Volume 180 / Number 3 / July 2015 / Pages 345-377

Technical Note / dx.doi.org/10.13182/NSE14-17