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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
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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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2018.1479091
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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2018.1538280
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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2018.1528803
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 | doi.org/10.1080/00295639.2018.1542867
Nonlinear Diffusion Acceleration of the Least-Squares Transport Equation in Geometries with Voids
Nuclear Science and Engineering | Volume 193 | Number 5 | May 2019 | Pages 453-480
Technical Paper | 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 | 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 | 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 | doi.org/10.1080/00295639.2018.1554173
Large-Scale Application of the Constraint Annealing Method for Pressurized Water Reactor Core Design Optimization
Nuclear Science and Engineering | Volume 193 | Number 5 | May 2019 | Pages 523-536
Technical Paper | 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 | 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 | doi.org/10.1080/00295639.2018.1542879
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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2018.1560758
The Roussopoulos and Schwinger Functionals for Nuclear Systems Involving Imprecisely Known Fluxes and Parameters: Distinctions and Equivalences
Nuclear Science and Engineering | Volume 193 | Number 7 | July 2019 | Pages 681-721
Technical Paper | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2019.1618074
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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2019.1574118
Alternative Adjoint Boltzmann Transport Operators in Alternative Hilbert Spaces in Spherical Geometry: Theory and Paradigm Applications
Nuclear Science and Engineering | Volume 193 | Number 9 | September 2019 | Pages 927-947
Technical Paper | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2019.1596721
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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2019.1599607
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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2019.1622927
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2019.1642675
