ANS / Publications / Journals / Nuclear Science and Engineering

Extremely Accurate Sequential Verification of RELAP5-3D

G. L. Mesina, D. L. Aumiller, F. X. Buschman

Nuclear Science and Engineering / Volume 182 / Number 1 / January 2016 / Pages 1-12

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NSE14-151

Standardized Consolidated Calculated and Reference Experimental Database (SCCRED): A Supporting Tool for V&V and Uncertainty Evaluation of Best-Estimate System Codes for Licensing Applications

A. Petruzzi, F. D'Auria

Nuclear Science and Engineering / Volume 182 / Number 1 / January 2016 / Pages 13-53

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NSE15-79

Hyperbolicity Criteria for System of Field Equations of One-Dimensional Two-Phase Flow with Compressible Components

Igor Arshavsky

Nuclear Science and Engineering / Volume 182 / Number 1 / January 2016 / Pages 54-70

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NSE14-144

Development of Governing Equations Based on Six Fields for the RELAP Code

Glenn A. Roth, Fatih Aydogan

Nuclear Science and Engineering / Volume 182 / Number 1 / January 2016 / Pages 71-82

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NSE14-149

Modeling Moving Systems with RELAP5-3D

G. L. Mesina, D. L. Aumiller, F. X. Buschman, M. R. Kyle

Nuclear Science and Engineering / Volume 182 / Number 1 / January 2016 / Pages 83-95

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NSE15-3

Implementation and Assessment of Moody Homogeneous Equilibrium Critical Flow Model of RELAP5-3D

Liang-Che Dai, Chung-Yu Yang, Yng-Ruey Yuann, Bau-Shei Pei, Chun-Kuan Shih

Nuclear Science and Engineering / Volume 182 / Number 1 / January 2016 / Pages 96-103

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NSE14-145

New Simulation Schemes and Capabilities for the PHISICS/RELAP5-3D Coupled Suite

C. Rabiti, A. Alfonsi, A. Epiney

Nuclear Science and Engineering / Volume 182 / Number 1 / January 2016 / Pages 104-118

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NSE14-143

Qualitative and Quantitative Evaluation of Coupling Approaches for Coupling of RELAP5 and LabVIEW

Zheng Fu, Joshua Pack, Fatih Aydogan

Nuclear Science and Engineering / Volume 182 / Number 1 / January 2016 / Pages 119-134

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NSE15-4

Improved Mixed Oxide Fuel Calculations with the Evaluated Nuclear Data Library JEFF-3.2

G. Noguere, D. Bernard, P. Blaise, O. Bouland, L. Leal, P. Leconte, O. Litaize, Y. Peneliau, B. Roque, A. Santamarina, J.-F. Vidal

Nuclear Science and Engineering / Volume 182 / Number 2 / February 2016 / Pages 135-150

Technical Paper / dx.doi.org/10.13182/NSE15-9

A Linear Source Approximation Scheme for the Method of Characteristics

Rodolfo M. Ferrer, Joel D. Rhodes III

Nuclear Science and Engineering / Volume 182 / Number 2 / February 2016 / Pages 151-165

Technical Paper / dx.doi.org/10.13182/NSE15-6

Development and Evaluation of High-Fidelity Product and Evenly Spaced Angular Quadratures for Three-Dimensional Discrete Ordinates Calculations with Large Air Regions

Daniel B. Fromowitz, Gary B. Zeigler

Nuclear Science and Engineering / Volume 182 / Number 2 / February 2016 / Pages 166-180

Technical Paper / dx.doi.org/10.13182/NSE14-49

Fission and Surface Source Iteration Method for Domain Decomposed Monte Carlo Whole-Core Calculation

YuGwon Jo, Nam Zin Cho

Nuclear Science and Engineering / Volume 182 / Number 2 / February 2016 / Pages 181-196

Technical Paper / dx.doi.org/10.13182/NSE14-150

Design Space Analysis for Breed-and-Burn Reactor Cores

Staffan Qvist, Ehud Greenspan

Nuclear Science and Engineering / Volume 182 / Number 2 / February 2016 / Pages 197-212

Technical Paper / dx.doi.org/10.13182/NSE14-135

Developments in Core-Barrel Motion Monitoring and Applications to the Ringhals PWR Units

Imre Pázsit, Cristina Montalvo, Henrik Nylén, Tell Andersson, Augusto Hernández-Solís, Petty Bernitt Cartemo

Nuclear Science and Engineering / Volume 182 / Number 2 / February 2016 / Pages 213-227

Technical Paper / dx.doi.org/10.13182/NSE15-14

Online Monitoring and Prognostics for Passive Components in Nuclear Power Plants

Pradeep Ramuhalli, Surajit Roy, Jangbom Chai

Nuclear Science and Engineering / Volume 182 / Number 2 / February 2016 / Pages 228-242

Technical Paper / dx.doi.org/10.13182/NSE14-127

Quantifying 3-D Positional Uncertainty of Radiological Material from Nuclear Detonation Videos

Daniel T. Schmitt, Robert Slaughter, Gilbert L. Peterson

Nuclear Science and Engineering / Volume 182 / Number 2 / February 2016 / Pages 243-255

Technical Paper / dx.doi.org/10.13182/NSE14-141

Neutron Emission Spectra of Triton Beams of 20.22-MeV Fully Stopped in Targets of H₂O, D₂O, LiF, Si, Ni, Mo, Ta, W, Pt, and Au

M. Drosg, D. M. Drake

Nuclear Science and Engineering / Volume 182 / Number 2 / February 2016 / Pages 256-260

Technical Note / dx.doi.org/10.13182/NSE15-17

Effects and Modeling of Power History in Thorium-Based Fuels in Pressure-Tube Heavy Water Reactors

Blair P. Bromley, Geoffrey W. R. Edwards, Pranavan Sambavalingam

Nuclear Science and Engineering / Volume 182 / Number 3 / March 2016 / Pages 263-286

Technical Paper / dx.doi.org/10.13182/NSE15-19

Mesh-Free Simulation of Aerosol Evolution

Shawn A. Campbell, John Palsmeier, Sudarshan K. Loyalka

Nuclear Science and Engineering / Volume 182 / Number 3 / March 2016 / Pages 287-296

Technical Paper / dx.doi.org/10.13182/NSE15-40

Higher-Order Chebyshev Rational Approximation Method and Application to Burnup Equations

Maria Pusa

Nuclear Science and Engineering / Volume 182 / Number 3 / March 2016 / Pages 297-318

Technical Paper / dx.doi.org/10.13182/NSE15-26

Hydrodynamically Developing and Fully Developed Laminar Flows in a Semicircular Duct: Analytical and Computational Analyses

Sai K. Mylavarapu, Xiaodong Sun, Richard N. Christensen

Nuclear Science and Engineering / Volume 182 / Number 3 / March 2016 / Pages 319-331

Technical Paper / dx.doi.org/10.13182/NSE14-107

SCALE Continuous-Energy Eigenvalue Sensitivity Coefficient Calculations

Christopher M. Perfetti, Bradley T. Rearden, William R. Martin

Nuclear Science and Engineering / Volume 182 / Number 3 / March 2016 / Pages 332-353

Technical Paper / dx.doi.org/10.13182/NSE15-12

Development of a Generalized Perturbation Theory Method for Sensitivity Analysis Using Continuous-Energy Monte Carlo Methods

Christopher M. Perfetti, Bradley T. Rearden

Nuclear Science and Engineering / Volume 182 / Number 3 / March 2016 / Pages 354-368

Technical Paper / dx.doi.org/10.13182/NSE15-13

An Implicit Correlation Method for COMET Core Eigenvalue Uncertainty Analysis

Dingkang Zhang, Farzad Rahnema

Nuclear Science and Engineering / Volume 182 / Number 3 / March 2016 / Pages 369-376

Technical Paper / dx.doi.org/10.13182/NSE15-15

The Use of Nuclear Data as Nuisance Parameters in the Integral Data Assimilation of the PROFIL Experiments

E. Privas, P. Archier, C. De Saint Jean, G. Noguere, J. Tommasi

Nuclear Science and Engineering / Volume 182 / Number 3 / March 2016 / Pages 377-393

Technical Paper / dx.doi.org/10.13182/NSE15-21

The Collision Probability Method in Today’s Computer Environment

Dimitar Altiparmakov, Robert Wiersma

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 395-416

Technical Paper / dx.doi.org/10.13182/NSE15-28

Discrete Ordinates Method for the Transport Equation Preserving One-Dimensional Spherical Symmetry in Two-Dimensional Cylindrical Geometry

F. Chaland, G. Samba

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 417-434

Technical Paper / dx.doi.org/10.13182/NSE15-38

A Multilevel Quasi-Static Kinetics Method for Pin-Resolved Transport Transient Reactor Analysis

Ang Zhu, Yunlin Xu, Thomas Downar

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 435-451

Technical Paper / dx.doi.org/10.13182/NSE15-39

A Heat Conduction and Convection Analytical Benchmark for Adjoint Solution Verification of Computational Fluid Dynamics Codes Used in Reactor Design

Dan G. Cacuci, Ruixian Fang, Milica Ilic, Madalina C. Badea

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 452-480

Technical Paper / dx.doi.org/10.13182/NSE15-69

Neutron Multiplicity Counting: Credible Regions for Reconstruction Parameters

Jérôme M. Verbeke

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 481-501

Technical Paper / dx.doi.org/10.13182/NSE15-35

Nuclear Fuel Cycle Transition Analysis Under Uncertainty

U. B. Phathanapirom, E. A. Schneider

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 502-522

Technical Paper / dx.doi.org/10.13182/NSE15-25

Accident-Tolerant-Fuel Performance Analysis of APMT Steel Clad/UO₂ Fuel and APMT Steel Clad/UN-U₃Si₅ Fuel Concepts

Jack Galloway, Cetin Unal

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 523-537

Technical Paper / dx.doi.org/10.13182/NSE15-7

CriSAA: A Simulation Code for Evaluation of Criticality Transients Involving Low Source Start-Up

Jun-Yun Yang, Xiao Gang, Yang-Jun Ying

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 538-554

Technical Paper / dx.doi.org/10.13182/NSE15-44

Uniform Tally Density–Based Strategy for Efficient Global Tallying in Monte Carlo Criticality Calculation

Danhua ShangGuan, Gang Li, Baoyin Zhang, Li Deng, Yan Ma, Yuanguan Fu, Rui Li,Xiaoli Hu

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 555-562

Technical Paper / dx.doi.org/10.13182/NSE15-32

Estimation of Double-Differential Angle-Dependent Neutron Production Cross Sections from Tritons on ¹⁹⁷Au at Energies from 5.97 to 19.14 MeV

Manfred Drosg, Bernard Hoop

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 563-570

Technical Note / dx.doi.org/10.13182/NSE15-57