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Volume 184

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Number 1

Inverse Predictive Modeling of a Spent-Fuel Dissolver Model

James J. Peltz, Dan G. Cacuci

Nuclear Science and Engineering / Volume 184 / Number 1 / September 2016 / Pages 1-15

Technical Paper / dx.doi.org/10.13182/NSE16-50

The Second-Order Adjoint Sensitivity Analysis Methodology for Nonlinear Systems—I: Theory

Dan G. Cacuci

Nuclear Science and Engineering / Volume 184 / Number 1 / September 2016 / Pages 16-30

Technical Paper / dx.doi.org/10.13182/NSE16-16

The Second-Order Adjoint Sensitivity Analysis Methodology for Nonlinear Systems—II: Illustrative Application to a Nonlinear Heat Conduction Problem

Dan G. Cacuci

Nuclear Science and Engineering / Volume 184 / Number 1 / September 2016 / Pages 31-52

Technical Paper / dx.doi.org/10.13182/NSE16-31

Continuous-Energy Sensitivity Coefficients in the MORET Code

Alexis Jinaphanh, Nicolas Leclaire, Bertrand Cochet

Nuclear Science and Engineering / Volume 184 / Number 1 / September 2016 / Pages 53-68

Technical Paper / dx.doi.org/10.13182/NSE16-2

Testing the Sampling-Based NUSS-RF Tool for the Nuclear Data–Related Global Sensitivity Analysis with Monte Carlo Neutronics Calculations

Ting Zhu, Alexander Vasiliev, Hakim Ferroukhi, Dimitri Rochman, Andreas Pautz

Nuclear Science and Engineering / Volume 184 / Number 1 / September 2016 / Pages 69-83

Technical Paper / dx.doi.org/10.13182/NSE14-142

A Phonon-Based Covariance Methodology for ENDF S(α, β) and Thermal Neutron Inelastic Scattering Cross Sections

Jesse C. Holmes, Ayman I. Hawari, Michael L. Zerkle

Nuclear Science and Engineering / Volume 184 / Number 1 / September 2016 / Pages 84-113

Technical Paper / dx.doi.org/10.13182/NSE15-89

Angle-Dependent Double-Differential Neutron Emission Cross Sections of 3H(t,n) Between 5.98 and 19.14 MeV and Evidence of 4H as Intermediate Reaction Product

M. Drosg, M. M. Steurer, E. Jericha, D. M. Drake

Nuclear Science and Engineering / Volume 184 / Number 1 / September 2016 / Pages 114-124

Technical Note / dx.doi.org/10.13182/NSE16-56

Passive Detection of Small Low-Emission Sources: Two-Dimensional Numerical Case Studies

A. Olson, A. Ciabatti, Y. Hristova, P. Kuchment, J. Ragusa, M. Allmaras

Nuclear Science and Engineering / Volume 184 / Number 1 / September 2016 / Pages 125-150

Technical Note / dx.doi.org/10.13182/NSE15-66

Number 2

Comparison of 1-D/1-D Fusion Method and 1-D/1-D Hybrid Method in Two-Dimensional Neutron Transport Problems: Convergence Analysis and Numerical Results

Seungsu Yuk, Nam Zin Cho

Nuclear Science and Engineering / Volume 184 / Number 2 / October 2016 / Pages 151-167

Technical Paper / dx.doi.org/10.13182/NSE15-128

A CMFD Acceleration Method for SP3 Advanced Nodal Method

Akio Yamamoto, Tatsuya Sakamoto, Tomohiro Endo

Nuclear Science and Engineering / Volume 184 / Number 2 / October 2016 / Pages 168-173

Technical Paper / dx.doi.org/10.13182/NSE16-53

Calculation of Higher-Order Fluxes in Symmetric Cores—I: Theory

Jean Tommasi, Maxence Maillot, Gérald Rimpault

Nuclear Science and Engineering / Volume 184 / Number 2 / October 2016 / Pages 174-189

Technical Paper / dx.doi.org/10.13182/NSE16-4

Calculation of Higher-Order Fluxes in Symmetric Cores—II: Implementation

Maxence Maillot, Jean Tommasi, Gérald Rimpault

Nuclear Science and Engineering / Volume 184 / Number 2 / October 2016 / Pages 190-207

Technical Paper / dx.doi.org/10.13182/NSE16-5

Analysis of Stabilization Techniques for CMFD Acceleration of Neutron Transport Problems

M. Jarrett, B. Kochunas, A. Zhu, T. Downar

Nuclear Science and Engineering / Volume 184 / Number 2 / October 2016 / Pages 208-227

Technical Paper / dx.doi.org/10.13182/NSE16-51

A Coarse-Mesh Coupled Neutronics and Thermal Fluids Method for Prismatic Cores

Kevin John Connolly, Alexander J. Huning, Farzad Rahnema, Srinivas Garimella

Nuclear Science and Engineering / Volume 184 / Number 2 / October 2016 / Pages 228-243

Technical Paper / dx.doi.org/10.13182/NSE15-105

Fourier Method for Calculating Fission Chain Neutron Multiplicity Distributions

David H. Chambers, Hema Chandrasekaran, Sean E. Walston

Nuclear Science and Engineering / Volume 184 / Number 2 / October 2016 / Pages 244-253

Technical Paper / dx.doi.org/10.13182/NSE15-109

Activation Cross Section for Reactions Induced by d-T Neutrons on Natural Yttrium

Junhua Luo, Li Jiang

Nuclear Science and Engineering / Volume 184 / Number 2 / October 2016 / Pages 254-262

Technical Paper / dx.doi.org/10.13182/NSE16-15

Experimental Investigation on Characteristics of Boiling Two-Phase-Flow Instability in a Parallel-Multichannel Natural-Circulation System

Sapna Singh, A. K. Nayak, J. Aparna

Nuclear Science and Engineering / Volume 184 / Number 2 / October 2016 / Pages 263-279

Technical Paper / dx.doi.org/10.13182/NSE15-125

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

M. P. Sharma, A. K. Nayak

Nuclear Science and Engineering / Volume 184 / Number 2 / October 2016 / Pages 280-291

Technical Paper / dx.doi.org/10.13182/NSE15-112

Number 3

Reactor Safety Gap Evaluation of Accident-Tolerant Components and Severe Accident Analysis

M. T. Farmer, R. Bunt, M. Corradini, P. Ellison, M. Francis, J. Gabor, R. Gauntt, C. Henry, R. Linthicum, W. Luangdilok, R. Lutz, C. Paik, M. Plys, C. Rabiti, J. Rempe, K. Robb, R. Wachowiak

Nuclear Science and Engineering / Volume 184 / Number 3 / November 2016 / Pages 293-304

Technical Paper / dx.doi.org/10.13182/NSE16-13

A Regulator’s Perspective on the State of the Art in Nuclear Thermal Hydraulics

Stephen M. Bajorek

Nuclear Science and Engineering / Volume 184 / Number 3 / November 2016 / Pages 305-311

Technical Paper / dx.doi.org/10.13182/NSE16-21

DNS–Assisted Modeling of Bubbly Flows in Vertical Channels

Gretar Tryggvason, Ming Ma, Jiacai Lu

Nuclear Science and Engineering / Volume 184 / Number 3 / November 2016 / Pages 312-320

Technical Paper / dx.doi.org/10.13182/NSE16-10

Analytical Stability Analogue for a Single-Phase Natural-Circulation Loop

Yousef M. Farawila, Donald R. Todd, Maurice J. Ades, José N. Reyes Jr.

Nuclear Science and Engineering / Volume 184 / Number 3 / November 2016 / Pages 321-333

Technical Paper / dx.doi.org/10.13182/NSE16-24

Symbolic Dynamics Applied to the Identification of Flow Patterns Inside Tube Banks

Alexandre Vagtinski de Paula, Luiz Augusto Magalhães Endres, Sergio Viçosa Möller

Nuclear Science and Engineering / Volume 184 / Number 3 / November 2016 / Pages 334-345

Technical Paper / dx.doi.org/10.13182/NSE16-30

Use of White Noise in TRACE/PARCS Analysis of ATWS with Instability

Tarek Zaki, Peter Yarsky

Nuclear Science and Engineering / Volume 184 / Number 3 / November 2016 / Pages 346-352

Technical Paper / dx.doi.org/10.13182/NSE16-14

Effect of Collision Force on Well-Posedness and Stability of the Two-Fluid Model for Vertical Bubbly Flows

Avinash Vaidheeswaran, William D. Fullmer, Martin Lopez de Bertodano

Nuclear Science and Engineering / Volume 184 / Number 3 / November 2016 / Pages 353-362

Technical Paper / dx.doi.org/10.13182/NSE16-23

Spectral Analysis of Single- and Two-Phase Bubbly DNS in Different Geometries

C. S. Brown, I. A. Bolotnov

Nuclear Science and Engineering / Volume 184 / Number 3 / November 2016 / Pages 363-376

Technical Paper / dx.doi.org/10.13182/NSE15-126

Phase-Field Modeling of Binary Eutectic Alloy Solidification with Convection

Stefan Meyer, Ivan Otic, Xu Cheng

Nuclear Science and Engineering / Volume 184 / Number 3 / November 2016 / Pages 377-387

Technical Paper / dx.doi.org/10.13182/NSE16-6

Sampling Variance and Bias of the Wilks Conservative Estimate of Confidence Intervals

Jan Peter Hessling

Nuclear Science and Engineering / Volume 184 / Number 3 / November 2016 / Pages 388-399

Technical Paper / dx.doi.org/10.13182/NSE16-8

Global Sensitivity Analysis of Transient Code Output Applied to a Reflood Experiment Model Using the TRACE Code

Damar Wicaksono, Omar Zerkak, Andreas Pautz

Nuclear Science and Engineering / Volume 184 / Number 3 / November 2016 / Pages 400-429

Technical Paper / dx.doi.org/10.13182/NSE16-37

Methodology for Characterizing Representativeness Uncertainty in Orifice Plate Mass Flow Rate Measurements Using CFD Simulations

Uuganbayar Otgonbaatar, Emilio Baglietto, Neil Todreas

Nuclear Science and Engineering / Volume 184 / Number 3 / November 2016 / Pages 430-440

Technical Paper / dx.doi.org/10.13182/NSE16-9

A Discussion of Uncertainty Quantification for CHF as Performed in COBRA-IE

David L. Aumiller, Michael J. Meholic

Nuclear Science and Engineering / Volume 184 / Number 3 / November 2016 / Pages 441-452

Technical Paper / dx.doi.org/10.13182/NSE16-41

An Assessment of Void Fraction Data with COBRA-IE

David L. Aumiller, Michael J. Meholic

Nuclear Science and Engineering / Volume 184 / Number 3 / November 2016 / Pages 453-462

Technical Paper / dx.doi.org/10.13182/NSE16-42

Large Open Region Interfacial Drag Modeling Package in COBRA-IE

David L. Aumiller, Jeffrey W. Lane

Nuclear Science and Engineering / Volume 184 / Number 3 / November 2016 / Pages 463-471

Technical Paper / dx.doi.org/10.13182/NSE16-12

Number 4

A Collision Probability and MOC-Based Lattice and Burnup Code for Analysis of LWR Fuel Assemblies

Sherly Ray, S. B. Degweker, Rashmi Rai, K. P. Singh

Nuclear Science and Engineering / Volume 184 / Number 4 / December 2016 / Pages 473-494

Technical Paper / dx.doi.org/10.13182/NSE15-127

Heterogeneous Pseudo-Resonant Isotope Method for Resolved Resonance Interference Treatment in Resonance Self-Shielding Calculation

Tiejun Zu, Qian Zhang, Hongchun Wu, Liangzhi Cao, Qingming He, Won Sik Yang

Nuclear Science and Engineering / Volume 184 / Number 4 / December 2016 / Pages 495-513

Technical Paper / dx.doi.org/10.13182/NSE16-65

Nonlinear Diffusion Acceleration Method with Multigrid in Energy for k-Eigenvalue Neutron Transport Problems

Luke R. Cornejo, Dmitriy Y. Anistratov

Nuclear Science and Engineering / Volume 184 / Number 4 / December 2016 / Pages 514-526

Technical Paper / dx.doi.org/10.13182/NSE16-78

Parallel Sn Sweep Scheduling Algorithm on Unstructured Grids for Multigroup Time-Dependent Particle Transport Equations

Jie Liu, Lihua Chi, Wang QingLin, Gong Chunye, Jiang Jie, Gan Xinbiao, Li Shengguo, Qingfeng Hu, Tom Masterson

Nuclear Science and Engineering / Volume 184 / Number 4 / December 2016 / Pages 527-536

Technical Paper / dx.doi.org/10.13182/NSE15-53

Stochastic Theory of the Fission Chamber Current Generated by Non-Poissonian Neutrons

Lénard Pál, Imre Pázsit

Nuclear Science and Engineering / Volume 184 / Number 4 / December 2016 / Pages 537-550

Technical Paper / dx.doi.org/10.13182/NSE16-18

Monte Carlo Approach of Effective Delayed Neutron Fraction by k-Ratio Method with External Neutron Source

Masao Yamanaka, Cheol Ho Pyeon, Tsuyoshi Misawa

Nuclear Science and Engineering / Volume 184 / Number 4 / December 2016 / Pages 551-560

Technical Paper / dx.doi.org/10.13182/NSE15-107

Ranking the Importance of Nuclear Reactions for Activation and Transmutation Events

Wayne Arter, J. Guy Morgan, Samuel D. Relton, Nicholas J. Higham

Nuclear Science and Engineering / Volume 184 / Number 4 / December 2016 / Pages 561-574

Technical Paper / dx.doi.org/10.13182/NSE15-23

Operational Experience Data Analysis on Events Related to Maintenance at Nuclear Power Plants

Antonio Ballesteros, Radian Sanda, Michael Maqua, Jean-Luc Stephan

Nuclear Science and Engineering / Volume 184 / Number 4 / December 2016 / Pages 575-583

Technical Paper / dx.doi.org/10.13182/NSE16-80

Pulsed Neutron Source Measurements in the BRAHMMA Accelerator-Driven Subcritical System

Tushar Roy, Nirmal Ray, Shefali Bajpai, Tarun Patel, Mayank Shukla, Yogesh Kashyap, Amar Sinha, S. C. Gadkari

Nuclear Science and Engineering / Volume 184 / Number 4 / December 2016 / Pages 584-590

Technical Paper / dx.doi.org/10.13182/NSE16-81

High-Order Linear Discontinuous and Diamond Differencing Schemes Along Cyclic Characteristics

Alain Hébert

Nuclear Science and Engineering / Volume 184 / Number 4 / December 2016 / Pages 591-603

Technical Note / dx.doi.org/10.13182/NSE16-82

 
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