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Volume 193

Number 1-2 | Number 3 | Number 4 | Number 5 | Number 6 | Number 7 | Number 8 | Number 9 | Number 10 | Number 11 | Number 12

Number 1-2

Numerical Simulation of Complete Pool Boiling Curves: From Nucleation to Critical Heat Flux Through Transition Boiling to Film Boiling

Xiaojing Ma, Ping Cheng

Nuclear Science and Engineering / Volume 193 / Number 1-2 / January-February 2019 / Pages 1-13

Critical Review – Selected papers from NURETH 2017 / dx.doi.org/10.1080/00295639.2018.1504566

Review on Thermal-Hydraulic Characteristics of Nuclear Reactors Under Ocean Conditions

Sipeng Wang, Bao-Wen Yang, Zhaobo Zhou, Jianping Long

Nuclear Science and Engineering / Volume 193 / Number 1-2 / January-February 2019 / Pages 14-32

Critical Review – Selected papers from NURETH 2017 / dx.doi.org/10.1080/00295639.2018.1512791

A Review of Void Drift Models in Subchannel Analysis

Hu Mao, Bao-Wen Yang, Sipeng Wang

Nuclear Science and Engineering / Volume 193 / Number 1-2 / January-February 2019 / Pages 33-45

Critical Review – Selected papers from NURETH 2017 / dx.doi.org/10.1080/00295639.2018.1525987

Interface Tracking Investigation of Geometric Effects on the Bubbly Flow in PWR Subchannels

Jun Fang, Joseph J. Cambareri, Michel Rasquin, Andre Gouws, Ramesh Balakrishnan, Kenneth E. Jansen, Igor A. Bolotnov

Nuclear Science and Engineering / Volume 193 / Number 1-2 / January-February 2019 / Pages 46-62

Technical Paper – Selected papers from NURETH 2017 / dx.doi.org/10.1080/00295639.2018.1499280

A Review of the CFD Modeling Progress Triggered by ISP-47 on Containment Thermal Hydraulics

S. Kelm, H. Müller, H.-J. Allelein

Nuclear Science and Engineering / Volume 193 / Number 1-2 / January-February 2019 / Pages 63-80

Technical Paper – Selected papers from NURETH 2017 / dx.doi.org/10.1080/00295639.2018.1503858

Validation and Uncertainty Quantification for Wall Boiling Closure Relations in Multiphase-CFD Solver

Yang Liu, Nam Dinh

Nuclear Science and Engineering / Volume 193 / Number 1-2 / January-February 2019 / Pages 81-99

Technical Paper – Selected papers from NURETH 2017 / dx.doi.org/10.1080/00295639.2018.1512790

Gaussian Process–Based Inverse Uncertainty Quantification for TRACE Physical Model Parameters Using Steady-State PSBT Benchmark

Chen Wang, Xu Wu, Tomasz Kozlowski

Nuclear Science and Engineering / Volume 193 / Number 1-2 / January-February 2019 / Pages 100-114

Technical Paper – Selected papers from NURETH 2017 / dx.doi.org/10.1080/00295639.2018.1499279

Numerical Investigation of Dryout Heat Flux and Heat Transfer Characteristics in Core Debris Bed of SFR After Severe Accident

Bin Zhang, Mengwei Zhang, Cheng Peng, Jianqiang Shan, Baowen Yang, Yonggang Cao, Lixia Ren

Nuclear Science and Engineering / Volume 193 / Number 1-2 / January-February 2019 / Pages 115-130

Technical Paper - Selected papers from NURETH 2017 / dx.doi.org/10.1080/00295639.2018.1514177

Coupling Methods for HTR-PM Multicircuit Problem

Jianan Lu, Jiong Guo, Tomasz Kozlowski, Fu Li

Nuclear Science and Engineering / Volume 193 / Number 1-2 / January-February 2019 / Pages 131-146

Technical Paper – Selected papers from NURETH 2017 / dx.doi.org/10.1080/00295639.2018.1504545

On CCFL at a PWR Hot-Leg Pipe Geometry and Comparison Between Results in COLLIDER 1/4th- and Kobe 1/15th-Scaled Facilities

S. Al Issa, M. Murase, A. Tomiyama, K. Hayashi, R. Macián-Juan

Nuclear Science and Engineering / Volume 193 / Number 1-2 / January-February 2019 / Pages 147-159

Technical Paper – Selected papers from NURETH 2017 / dx.doi.org/10.1080/00295639.2018.1489627

Investigation of Local Heat Transfer Enhancement in Generic Liquid Metal–Cooled Fuel Assemblies with Empirical Models

Wadim Jaeger, Wolfgang Hering

Nuclear Science and Engineering / Volume 193 / Number 1-2 / January-February 2019 / Pages 160-170

Technical Paper – Selected papers from NURETH 2017 / dx.doi.org/10.1080/00295639.2018.1493855

An Experimental Study of Local Self-Similarity in the Mixing Transition of a Turbulent Free Jet

Benedikt Krohn, Sunming Qin, John Downing, Victor Petrov, Annalisa Manera

Nuclear Science and Engineering / Volume 193 / Number 1-2 / January-February 2019 / Pages 171-184

Technical Paper – Selected papers from NURETH 2017 / dx.doi.org/10.1080/00295639.2018.1507360

Heat Loss Simulations in Rod Bundle Tests

Aiguo Liu, Bao-Wen Yang, Yudong Zha

Nuclear Science and Engineering / Volume 193 / Number 1-2 / January-February 2019 / Pages 185-197

Technical Paper – Selected papers from NURETH 2017 / dx.doi.org/10.1080/00295639.2018.1525189

Experimental and Analytical Investigations of Aerosol Processes—Wash-Out and Wash-Down

M. Freitag, S. Gupta, S. Beck, M. Sonnenkalb

Nuclear Science and Engineering / Volume 193 / Number 1-2 / January-February 2019 / Pages 198-210

Technical Paper – Selected papers from NURETH 2017 / dx.doi.org/10.1080/00295639.2018.1479091

Number 3

Mesh-Free Simulation of Spatially Inhomogeneous Aerosols in Arbitrary Geometries

Matthew Boraas, Sudarshan K. Loyalka

Nuclear Science and Engineering / Volume 193 / Number 3 / March 2019 / Pages 211-232

Technical Paper / dx.doi.org/10.1080/00295639.2018.1516953

Assessment of the Lagrange Discrete Ordinates Equations for Three-Dimensional Neutron Transport

Kelly L. Rowland, Cory D. Ahrens, Steven Hamilton, R. N. Slaybaugh

Nuclear Science and Engineering / Volume 193 / Number 3 / March 2019 / Pages 233-252

Technical Paper / dx.doi.org/10.1080/00295639.2018.1509569

Utilization of Regionwise Even-Parity Discontinuity Factor to Reduce Discretization Error of MOC

Akio Yamamoto, Akinori Giho, Tomohiro Endo

Nuclear Science and Engineering / Volume 193 / Number 3 / March 2019 / Pages 253-268

Technical Paper / dx.doi.org/10.1080/00295639.2018.1516961

Neutron Transmission and Capture Measurements of 133Cs from 0.01 to 600 eV

R. C. Block, J. A. Burke, D. P. Barry, N. J. Drindak, G. Leinweber, K. E. Remley, R. V. Ballad, M. J. Rapp, Y. Danon

Nuclear Science and Engineering / Volume 193 / Number 3 / March 2019 / Pages 269-282

Technical Paper / dx.doi.org/10.1080/00295639.2018.1520526

Development of a Solver for Multi-Fluid and Multi-Pressure Model

Hao Zhang, Yanhua Yang

Nuclear Science and Engineering / Volume 193 / Number 3 / March 2019 / Pages 283-298

Technical Paper / dx.doi.org/10.1080/00295639.2018.1512788

Effects of Bubble Injection on Heat Transfer from a Volumetrically Heated Sulfate Salt Solution

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

Nuclear Science and Engineering / Volume 193 / Number 3 / March 2019 / Pages 299-313

Technical Paper / dx.doi.org/10.1080/00295639.2018.1514195

Uncertainty Propagation in Neutron Activation Cross-Section Measurement Using Unscented Transformation Method

Jagjit Singh Matharu, Vidya Devi

Nuclear Science and Engineering / Volume 193 / Number 3 / March 2019 / Pages 314-324

Technical Paper / dx.doi.org/10.1080/00295639.2018.1538280

Number 4

Approximate Methods for Inverting Generating Functions from the Pál-Bell Equations for Low Source Problems

M. M. R. Williams

Nuclear Science and Engineering / Volume 193 / Number 4 / April 2019 / Pages 327-345

Technical Paper / dx.doi.org/10.1080/00295639.2018.1531620

Validation and Verification of the Evaluated Electron Data Library in FRENSIE

Luke J. Kersting, Douglass Henderson, Alex Robinson, Eli Moll

Nuclear Science and Engineering / Volume 193 / Number 4 / April 2019 / Pages 346-367

Technical Paper / dx.doi.org/10.1080/00295639.2018.1525976

A Coupled Multiscale Approach to TREAT LEU Feedback Modeling Using a Binary-Collision Monte-Carlo–Informed Heat Source

Adam Zabriskie, Sebastian Schunert, Daniel Schwen, Javier Ortensi, Benjamin Baker, Yaqi Wang, Vincent Laboure, Mark DeHart, Wade Marcum

Nuclear Science and Engineering / Volume 193 / Number 4 / April 2019 / Pages 368-387

Technical Paper / dx.doi.org/10.1080/00295639.2018.1528802

A Weighted Least-Squares Transport Equation Compatible with Source Iteration and Voids

Hans R. Hammer, Jim E. Morel, Yaqi Wang

Nuclear Science and Engineering / Volume 193 / Number 4 / April 2019 / Pages 388-403

Technical Paper / dx.doi.org/10.1080/00295639.2018.1525977

Benchmarks of Criticality in Solid-Moderated and Solid-Reflected Cores at Kyoto University Critical Assembly

Masao Yamanaka, Cheol Ho Pyeon

Nuclear Science and Engineering / Volume 193 / Number 4 / April 2019 / Pages 404-416

Technical Paper / dx.doi.org/10.1080/00295639.2018.1525978

Modified Point-Kinetics Model for Neutron Precursors and Fission Product Behavior for Fluid-Fueled Molten Salt Reactors

M. Scott Greenwood, Ben Betzler

Nuclear Science and Engineering / Volume 193 / Number 4 / April 2019 / Pages 417-430

Technical Paper / dx.doi.org/10.1080/00295639.2018.1531619

Estimation Method of Prompt Neutron Decay Constant Reducing Higher Order Mode Effect by Linear Combination

Ryota Katano

Nuclear Science and Engineering / Volume 193 / Number 4 / April 2019 / Pages 431-439

Technical Paper / dx.doi.org/10.1080/00295639.2018.1528803

Number 5

Generation of Exact Discontinuity Factors for NEM Calculations with Two-by-Two Division per Fuel Assembly

HyeonTae Kim, Woosong Kim, Yonghee Kim

Nuclear Science and Engineering / Volume 193 / Number 5 / May 2019 / Pages 441-452

Technical Paper / dx.doi.org/10.1080/00295639.2018.1542867

Nonlinear Diffusion Acceleration of the Least-Squares Transport Equation in Geometries with Voids

Hans R. Hammer, Jim E. Morel, Yaqi Wang

Nuclear Science and Engineering / Volume 193 / Number 5 / May 2019 / Pages 453-480

Technical Paper / dx.doi.org/10.1080/00295639.2018.1542865

Development of Monte Carlo Neutron Transport Method-Based Supercritical Transient Code with Time-Dependent Feedback Capability

Delgersaikhan Tuya, Toru Obara

Nuclear Science and Engineering / Volume 193 / Number 5 / May 2019 / Pages 481-494

Technical Paper / dx.doi.org/10.1080/00295639.2018.1540209

Reactor Kinetics Using Partial Equations

E. F. Seleznev, V. Bereznev, I. Chernova

Nuclear Science and Engineering / Volume 193 / Number 5 / May 2019 / Pages 495-505

Technical Paper / dx.doi.org/10.1080/00295639.2018.1542866

Constraint Annealing Method for Solution of Multiconstrained Nuclear Fuel Cycle Optimization Problems

David J. Kropaczek, Ryan Walden

Nuclear Science and Engineering / Volume 193 / Number 5 / May 2019 / Pages 506-522

Technical Paper / dx.doi.org/10.1080/00295639.2018.1554173

Large-Scale Application of the Constraint Annealing Method for Pressurized Water Reactor Core Design Optimization

David J. Kropaczek, Ryan Walden

Nuclear Science and Engineering / Volume 193 / Number 5 / May 2019 / Pages 523-536

Technical Paper / dx.doi.org/10.1080/00295639.2018.1550970

Results of Three Neutron Diagnosed Subcritical Experiments

J. A. Gomez, P. E. Koehler, T. E. Cutler, A. DeYoung, J. T. Goorley, J. D. Hutchinson, G. McKenzie, G. L. Morgan, S. M. Mosby, W. L. Myers, R. S. Rundberg, V. W. Yuan

Nuclear Science and Engineering / Volume 193 / Number 5 / May 2019 / Pages 537-548

Technical Paper / dx.doi.org/10.1080/00295639.2018.1545956

Radioactive Decay Computation with Dynamic Source Terms

DeeEarl Vaden, Tae-Sic Yoo

Nuclear Science and Engineering / Volume 193 / Number 5 / May 2019 / Pages 549-553

Technical Note / dx.doi.org/10.1080/00295639.2018.1542879

Number 6

Application of the Second-Order Comprehensive Adjoint Sensitivity Analysis Methodology to Compute First- and Second-Order Sensitivities of Flux Functionals in a Multiplying System with Source

Dan Gabriel Cacuci

Nuclear Science and Engineering / Volume 193 / Number 6 / June 2019 / Pages 555-600

Technical Paper / dx.doi.org/10.1080/00295639.2018.1553910

The Subray Method of Characteristics

Aaron M. Graham, Benjamin S. Collins, Thomas J. Downar

Nuclear Science and Engineering / Volume 193 / Number 6 / June 2019 / Pages 601-621

Technical Paper / dx.doi.org/10.1080/00295639.2018.1550988

Compression of Assembly Power Form Factors for Core Calculations

Daniele Tomatis

Nuclear Science and Engineering / Volume 193 / Number 6 / June 2019 / Pages 622-637

Technical Paper / dx.doi.org/10.1080/00295639.2018.1553428

Improvement of the VVER-1200 Fuel Cycle by Introducing Thorium with Different Fissile Material in Blanket-Seed Assembly

A. Abdelghafar Galahom

Nuclear Science and Engineering / Volume 193 / Number 6 / June 2019 / Pages 638-651

Technical Paper / dx.doi.org/10.1080/00295639.2018.1560757

Generalized Partitioned Matrix Acceleration for Variational Nodal Diffusion Method

Yongping Wang, Yunzhao Li, Tengfei Zhang, E. E. Lewis, M. A. Smith, W. S. Yang, Hongchun Wu

Nuclear Science and Engineering / Volume 193 / Number 6 / June 2019 / Pages 652-662

Technical Note / dx.doi.org/10.1080/00295639.2018.1542883

A Note on the Nomenclature in Neutron Multiplicity Mathematics

Tony H. Shin, Jesson Hutchinson, Rian Bahran, Sara A. Pozzi

Nuclear Science and Engineering / Volume 193 / Number 6 / June 2019 / Pages 663-679

Technical Note / dx.doi.org/10.1080/00295639.2018.1560758

Number 7

The Roussopoulos and Schwinger Functionals for Nuclear Systems Involving Imprecisely Known Fluxes and Parameters: Distinctions and Equivalences

Dan Gabriel Cacuci

Nuclear Science and Engineering / Volume 193 / Number 7 / July 2019 / Pages 681-721

Technical Paper / dx.doi.org/10.1080/00295639.2018.1564504

A Multilevel in Space and Energy Solver for 3-D Multigroup Diffusion and Coarse-Mesh Finite Difference Eigenvalue Problems

Ben C. Yee, Brendan Kochunas, Edward W. Larsen

Nuclear Science and Engineering / Volume 193 / Number 7 / July 2019 / Pages 722-745

Technical Paper / dx.doi.org/10.1080/00295639.2018.1562777

An Efficient Sweep-Based Solver for the SN Equations on High-Order Meshes

T. S. Haut, P. G. Maginot, V. Z. Tomov, B. S. Southworth, T. A. Brunner, T. S. Bailey

Nuclear Science and Engineering / Volume 193 / Number 7 / July 2019 / Pages 746-759

Technical Paper / dx.doi.org/10.1080/00295639.2018.1562778

Calculations and Evaluations of Neutron-Induced Reactions on 180m,181Ta

Xinwu Su, Yinlu Han

Nuclear Science and Engineering / Volume 193 / Number 7 / July 2019 / Pages 760-775

Technical Paper / dx.doi.org/10.1080/00295639.2018.1560775

Universal Methodology for Statistical Error and Convergence of Correlated Monte Carlo Tallies

Taro Ueki

Nuclear Science and Engineering / Volume 193 / Number 7 / July 2019 / Pages 776-789

Technical Paper / dx.doi.org/10.1080/00295639.2018.1562779

Modeling for Late-Phase Hydrogen Generation in a Degraded Core

Robert E. Henry

Nuclear Science and Engineering / Volume 193 / Number 7 / July 2019 / Pages 790-799

Technical Paper / dx.doi.org/10.1080/00295639.2018.1560855

ADDENDUM: Neutron Time Interval Distributions with Background Neutrons

Manoj Prasad, Neal Snyderman, Sean Walston

Nuclear Science and Engineering / Volume 193 / Number 7 / July 2019 / Pages 800-802

Addendum / dx.doi.org/10.1080/00295639.2019.1618074

Number 8

Iteration Methods with Multigrid in Energy for Eigenvalue Neutron Diffusion Problems

Luke R. Cornejo, Dmitriy Y. Anistratov, Kord Smith

Nuclear Science and Engineering / Volume 193 / Number 8 / August 2019 / Pages 803-827

Technical Paper / dx.doi.org/10.1080/00295639.2019.1573601

Consistent pCMFD Acceleration Schemes of the Three-Dimensional Transport Code PROTEUS-MOC

Guangchun Zhang, Albert Hsieh, Won Sik Yang, Yeon Sang Jung

Nuclear Science and Engineering / Volume 193 / Number 8 / August 2019 / Pages 828-853

Technical Paper / dx.doi.org/10.1080/00295639.2018.1560854

Calculating Time Eigenvalues of the Neutron Transport Equation with Dynamic Mode Decomposition

Ryan G. McClarren

Nuclear Science and Engineering / Volume 193 / Number 8 / August 2019 / Pages 854-867

Technical Paper / dx.doi.org/10.1080/00295639.2018.1565014

A New Approach to Monte Carlo in High Temperature Reactors

Indrajeet Singh, S. B. Degweker, Amod Kishore Mallick, Anurag Gupta

Nuclear Science and Engineering / Volume 193 / Number 8 / August 2019 / Pages 868-883

Technical Paper / dx.doi.org/10.1080/00295639.2019.1576453

Key Results from Detailed Nondestructive Examinations of 25 Pressurized Water Reactor High Burnup Spent Nuclear Fuel Rods

Rose Montgomery, Robert N. Morris, Bruce Bevard, John Scaglione

Nuclear Science and Engineering / Volume 193 / Number 8 / August 2019 / Pages 884-902

Technical Paper / dx.doi.org/10.1080/00295639.2019.1573602

Tantalum, Titanium, and Zirconium Neutron Total Cross-Section Measurements from 0.4 to 25 MeV

M. J. Rapp, D. P. Barry, G. Leinweber, R. C. Block, B. E. Epping, T. H. Trumbull, Y. Danon

Nuclear Science and Engineering / Volume 193 / Number 8 / August 2019 / Pages 903-915

Technical Paper / dx.doi.org/10.1080/00295639.2019.1570750

An Estimation of Volatile Iodine in a Pool at Low pH and High Iodide Concentrations Under Irradiation

Thi Thanh Thuy Nguyen, Kwang Soon Ha, Jin Ho Song, Sung Il Kim

Nuclear Science and Engineering / Volume 193 / Number 8 / August 2019 / Pages 916-925

Technical Paper / dx.doi.org/10.1080/00295639.2019.1574118

Number 9

Alternative Adjoint Boltzmann Transport Operators in Alternative Hilbert Spaces in Spherical Geometry: Theory and Paradigm Applications

Dan Gabriel Cacuci

Nuclear Science and Engineering / Volume 193 / Number 9 / September 2019 / Pages 927-947

Technical Paper / dx.doi.org/10.1080/00295639.2019.1582934

Fission Matrix Decomposition Method for Criticality Calculations: Theory and Proof of Concept

Stefano Terlizzi, Dan Kotlyar

Nuclear Science and Engineering / Volume 193 / Number 9 / September 2019 / Pages 948-965

Technical Paper / dx.doi.org/10.1080/00295639.2019.1583948

Accelerating Monte Carlo Shielding Calculations in TRIPOLI-4 with a Deterministic Adjoint Flux

M. Nowak, D. Mancusi, D. Sciannandrone, E. Masiello, H. Louvin, E. Dumonteil

Nuclear Science and Engineering / Volume 193 / Number 9 / September 2019 / Pages 966-981

Technical Paper / dx.doi.org/10.1080/00295639.2019.1578568

High-Order Lax-Friedrichs WENO Fast Sweeping Methods for the SN Neutron Transport Equation

Dean Wang, Tseelmaa Byambaakhuu

Nuclear Science and Engineering / Volume 193 / Number 9 / September 2019 / Pages 982-990

Technical Paper / dx.doi.org/10.1080/00295639.2019.1582316

A New Interpretation of Discontinuity Factor

Akio Yamamoto, Tomohiro Endo

Nuclear Science and Engineering / Volume 193 / Number 9 / September 2019 / Pages 991-997

Technical Paper / dx.doi.org/10.1080/00295639.2019.1579514

Helium Tribology of Inconel 617 at Elevated Temperatures up to 950°C: Parametric Study

Md Saifur Rahman, Jie Ding, Ali Beheshti, Xinghang Zhang, Andreas A. Polycarpou

Nuclear Science and Engineering / Volume 193 / Number 9 / September 2019 / Pages 998-1012

Technical Paper / dx.doi.org/10.1080/00295639.2019.1582315

Temperature Reactivity Control of Calcium Hydride–Moderated Small Reactor Core with Poison Nuclides

Rei Kimura, Satoshi Wada

Nuclear Science and Engineering / Volume 193 / Number 9 / September 2019 / Pages 1013-1022

Technical Paper / dx.doi.org/10.1080/00295639.2019.1576454

Integral Experiments on Critical Irradiation of 237Np and 241Am Foils at Kyoto University Critical Assembly

Cheol Ho Pyeon, Masao Yamanaka, Tadafumi Sano, Koichi Takamiya

Nuclear Science and Engineering / Volume 193 / Number 9 / September 2019 / Pages 1023-1032

Technical Paper / dx.doi.org/10.1080/00295639.2019.1603014

Investigation of Neutron Cross Section for Iron in the ENDF Library with Pulsed Sphere Measurements

Sushil Dhakal, Carl R. Brune, Thomas N. Massey, Steven M. Grimes, Alexander V. Voinov, Shamim Akhtar, Anthony P. D. Ramirez, Andrea L. Richard

Nuclear Science and Engineering / Volume 193 / Number 9 / September 2019 / Pages 1033-1043

Technical Paper / dx.doi.org/10.1080/00295639.2019.1591095

A Diffusion Monte Carlo–Based Algorithm for Estimation of Higher Modes of a Reactor

Argala Srivastava, K. P. Singh, Amod Kishore Mallick, Umasankari Kannan, S. B. Degweker

Nuclear Science and Engineering / Volume 193 / Number 9 / September 2019 / Pages 1044-1053

Technical Note / dx.doi.org/10.1080/00295639.2019.1596721

Number 10

Review of Hybrid Methods for Deep-Penetration Neutron Transport

Madicken Munk, Rachel N. Slaybaugh

Nuclear Science and Engineering / Volume 193 / Number 10 / October 2019 / Pages 1055-1089

Technical Paper / dx.doi.org/10.1080/00295639.2019.1586273

Estimating Code Biases for Criticality Safety Applications with Few Relevant Benchmarks

Christopher M. Perfetti, Bradley T. Rearden

Nuclear Science and Engineering / Volume 193 / Number 10 / October 2019 / Pages 1090-1128

Technical Paper / dx.doi.org/10.1080/00295639.2019.1604048

Numerical and Experimental Study on the Air Convective Heat Transfer Characteristics in Large-Scale Rectangular Channel with Asymmetric Heating Considering the Influence of Entry Form

Kashuai Du, Po Hu, Lefu Zhang, Weibo Wang

Nuclear Science and Engineering / Volume 193 / Number 10 / October 2019 / Pages 1129-1146

Technical Paper / dx.doi.org/10.1080/00295639.2019.1591094

Experimental Investigation of Natural Circulation During Air-Ingress Scenario in a Very High Temperature Reactor

Apoorva V. Rudra, Dinesh V. Kalaga, Masahiro Kawaji

Nuclear Science and Engineering / Volume 193 / Number 10 / October 2019 / Pages 1147-1159

Technical Paper / dx.doi.org/10.1080/00295639.2019.1595311

Fuzzy Logics as an Integral Part of Evolutionary Algorithms

Amit Thakur, Umasankari Kannan

Nuclear Science and Engineering / Volume 193 / Number 10 / October 2019 / Pages 1160-1171

Technical Paper / dx.doi.org/10.1080/00295639.2019.1599607

Number 11

Dynamic Mode Decomposition for Subcritical Metal Systems

Zachary K. Hardy, Jim E. Morel, Cory Ahrens

Nuclear Science and Engineering / Volume 193 / Number 11 / November 2019 / Pages 1173-1185

Technical Paper / dx.doi.org/10.1080/00295639.2019.1609317

Calculating the k-Eigenvalue Sensitivity to Typical Geometric Perturbations with the Adjoint-Weighted Method in the Continuous-Energy Reactor Monte Carlo Code RMC

Hao Li, Ganglin Yu, Shanfang Huang, Mengfei Zhou, Guanlin Shi, Kan Wang

Nuclear Science and Engineering / Volume 193 / Number 11 / November 2019 / Pages 1186-1218

Technical Paper / dx.doi.org/10.1080/00295639.2019.1614800

Multiblock Adaptive Mesh Refinement for the SN Transport Equation Based on Lattice Boltzmann Method

Yu Ma, Yahui Wang, Ming Xie

Nuclear Science and Engineering / Volume 193 / Number 11 / November 2019 / Pages 1219-1237

Technical Paper / dx.doi.org/10.1080/00295639.2019.1620052

Pinwise Diffusion Solution of Partially MOX-Loaded PWRs with the GPS (GET PLUS SPH) Method

Hwanyeal Yu, Jaeha Kim, Yonghee Kim

Nuclear Science and Engineering / Volume 193 / Number 11 / November 2019 / Pages 1238-1254

Technical Paper / dx.doi.org/10.1080/00295639.2019.1614367

Scoping Studies of Dopants for Stabilization of Uranium Nitride Fuel

Klara Insulander Björk, Aneta Herman, Marcus Hedberg, Christian Ekberg

Nuclear Science and Engineering / Volume 193 / Number 11 / November 2019 / Pages 1255-1264

Technical Paper / dx.doi.org/10.1080/00295639.2019.1614368

Importance of Voxel Size in Defect Localization Using Gamma-Ray Scattering

Akash Tondon, Mohinder Singh, B. S. Sandhu, Bhajan Singh

Nuclear Science and Engineering / Volume 193 / Number 11 / November 2019 / Pages 1265-1275

Technical Paper / dx.doi.org/10.1080/00295639.2019.1614802

Coupling of Neutronics and Thermal-Hydraulic Codes for Simulation of the MNSR Reactor

Jamal Al Zain, O. El Hajjaji, T. El Bardouni, Y. Boulaich

Nuclear Science and Engineering / Volume 193 / Number 11 / November 2019 / Pages 1276-1289

Technical Paper / dx.doi.org/10.1080/00295639.2019.1622927

Number 12

Polar Parity for Efficient Evaluation of Anisotropic Transverse Leakage in the 2D/1D Transport Method

Michael Jarrett, Brendan Kochunas, Edward Larsen, Thomas Downar

Nuclear Science and Engineering / Volume 193 / Number 12 / December 2019 / Pages 1291-1309

Technical Paper / dx.doi.org/10.1080/00295639.2019.1627176

Coupled Neutron and Gamma Heating Calculation Based on VARIANT Transport Solutions

P. Deng, B. K. Jeon, H. Park, W. S. Yang

Nuclear Science and Engineering / Volume 193 / Number 12 / December 2019 / Pages 1310-1338

Technical Paper / dx.doi.org/10.1080/00295639.2019.1621617

The Asymptotic Diffusion Limit of Numerical Schemes for the SN Transport Equation

Dean Wang

Nuclear Science and Engineering / Volume 193 / Number 12 / December 2019 / Pages 1339-1354

Technical Paper / dx.doi.org/10.1080/00295639.2019.1638660

A Directional Detector Response Function for Anisotropic Detectors

Cihangir Celik, Douglas E. Peplow, Gregory G. Davidson, Mathew W. Swinney

Nuclear Science and Engineering / Volume 193 / Number 12 / December 2019 / Pages 1355-1370

Technical Paper / dx.doi.org/10.1080/00295639.2019.1631028

Acceleration of the Power Method with Dynamic Mode Decomposition

Jeremy A. Roberts, Leidong Xu, Rabab Elzohery, Mohammad Abdo

Nuclear Science and Engineering / Volume 193 / Number 12 / December 2019 / Pages 1371-1378

Technical Paper / dx.doi.org/10.1080/00295639.2019.1634928

CFD Simulations of Molten Salt Reactor Experiment Core

Krishna Podila, Qi Chen, Yanfei Rao

Nuclear Science and Engineering / Volume 193 / Number 12 / December 2019 / Pages 1379-1393

Technical Paper / dx.doi.org/10.1080/00295639.2019.1627177

Application of Linear Combination Method to Pulsed Neutron Source Measurement at Kyoto University Critical Assembly

Ryota Katano, Masao Yamanaka, Cheol Ho Pyeon

Nuclear Science and Engineering / Volume 193 / Number 12 / December 2019 / Pages 1394-1402

Technical Paper / dx.doi.org/10.1080/00295639.2019.1624084

Critical Mass Flux of Subcooled Liquid Leakage in a Nuclear Plant

Songtao Yin, Hongdong Zhen, Lei Zhang, Bo Cheng, Ningning Wang, Haijun Wang

Nuclear Science and Engineering / Volume 193 / Number 12 / December 2019 / Pages 1403-1410

Technical Paper / dx.doi.org/10.1080/00295639.2019.1642675

 

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