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Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
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Three-Dimensional Pin-Resolved Transient Diffusion Analysis of PWR Core by the Hybrid Coarse-Mesh Finite Difference Algorithm
Jaeha Kim, Yonghee Kim
Nuclear Science and Engineering | Volume 194 | Number 1 | January 2020 | Pages 1-13
Technical Paper | doi.org/10.1080/00295639.2019.1642016
Deterministic Truncation of the Monte Carlo Transport Solution for Reactor Eigenvalue and Pinwise Power Distribution
Inhyung Kim, HyeonTae Kim, Yonghee Kim
Nuclear Science and Engineering | Volume 194 | Number 1 | January 2020 | Pages 14-31
Technical Paper | doi.org/10.1080/00295639.2019.1654815
Development of the Assembly-Level Monte Carlo Neutron Transport Code M3C for Reactor Physics Calculations
Anek Kumar, Umasankari Kannan, S. Ganesan
Nuclear Science and Engineering | Volume 194 | Number 1 | January 2020 | Pages 32-43
Technical Paper | doi.org/10.1080/00295639.2019.1645502
Generation of Multigroup Cross Sections with an Improved Monte Carlo Algorithm
Li Cheng, Bin Zhong, Huayun Shen, Zehua Hu, Baiwen Li
Nuclear Science and Engineering | Volume 194 | Number 1 | January 2020 | Pages 44-55
Technical Paper | doi.org/10.1080/00295639.2019.1650520
Derivation of the Two-Exponential Probability Density Function for Rossi-Alpha Measurements of Reflected Assemblies and Validation for the Special Case of Shielded Measurements
Michael Y. Hua, Jesson D. Hutchinson, George E. McKenzie, Tony H. Shin, Shaun D. Clarke, Sara A. Pozzi
Nuclear Science and Engineering | Volume 194 | Number 1 | January 2020 | Pages 56-68
Technical Paper | doi.org/10.1080/00295639.2019.1654327
Effects of Gamma Irradiation on the Morphological, Physical, and Thermal Properties of B4C/CF/PI/AA6061 Hybrid Composite Laminates
Xuelong Fu, Jie Tao, Dunwen Zuo
Nuclear Science and Engineering | Volume 194 | Number 1 | January 2020 | Pages 69-83
Technical Paper | doi.org/10.1080/00295639.2019.1654328
ADDENDUM: Approximate Methods for Inverting Generating Functions from the Pál-Bell Equations for Low Source Problems
M. M. R. Williams
Nuclear Science and Engineering | Volume 194 | Number 1 | January 2020 | Pages 84-85
Addendum | doi.org/10.1080/00295639.2019.1687193
Monte Carlo Solution of k-Eigenvalue Problem Using Subspace Iteration Method
Anurag Gupta, R. S. Modak
Nuclear Science and Engineering | Volume 194 | Number 2 | February 2020 | Pages 87-103
Technical Paper | doi.org/10.1080/00295639.2019.1668655
A Novel and Efficient Hybrid RSILU Preconditioner for the Parallel GMRES Solution of the Coarse Mesh Finite Difference Equations for Practical Reactor Simulations
Yunlin Xu, Chen Hao
Nuclear Science and Engineering | Volume 194 | Number 2 | February 2020 | Pages 104-119
Technical Paper | doi.org/10.1080/00295639.2019.1657322
A Transport-Free Method for Predicting the Post-Depletion Spatial Neutron Flux Distribution
Andrew E. Johnson, Dan Kotlyar
Nuclear Science and Engineering | Volume 194 | Number 2 | February 2020 | Pages 120-137
Technical Paper | doi.org/10.1080/00295639.2019.1661171
Systematic Measurements and Analyses for Lead Void Reactivity Worth in a Plutonium Core and Two Uranium Cores with Different Enrichments
M. Fukushima, J. Goda, A. Oizumi, J. Bounds, T. Cutler, T. Grove, D. Hayes, J. Hutchinson, G. McKenzie, A. McSpaden, R. Sanchez, J. Walker, K. Tsujimoto
Nuclear Science and Engineering | Volume 194 | Number 2 | February 2020 | Pages 138-153
Technical Paper | doi.org/10.1080/00295639.2019.1663089
Simulation of the Nondestructive Assay of 237Np Using Active Neutron Multiplicity Counting
Michael Y. Hua, Braden Goddard, Cody Lloyd, Evan C. Leppink, Sara A. Abraham, Jordan D. Noey, Shaun D. Clarke, Sara A. Pozzi
Nuclear Science and Engineering | Volume 194 | Number 2 | February 2020 | Pages 154-162
Technical Paper | doi.org/10.1080/00295639.2019.1654329
Preliminary Study of a Prismatic-Core Advanced High-Temperature Reactor Fuel Using Homogenization Double-Heterogeneous Method
Mohammad Alrwashdeh, Saeed A. Alameri, Ahmed K. Alkaabi
Nuclear Science and Engineering | Volume 194 | Number 2 | February 2020 | Pages 163-167
Technical Paper | doi.org/10.1080/00295639.2019.1672511
Review of Progress in Coated Fuel Particle Performance Analysis
Nairi Baghdasaryan, Tomasz Kozlowski
Nuclear Science and Engineering | Volume 194 | Number 3 | March 2020 | Pages 169-180
Critical Review | doi.org/10.1080/00295639.2019.1686882
Radiation Dose Analysis in Criticality Accident of Fuel Debris in Water
Kodai Fukuda, Delgersaikhan Tuya, Jun Nishiyama, Toru Obara
Nuclear Science and Engineering | Volume 194 | Number 3 | March 2020 | Pages 181-189
Technical Paper | doi.org/10.1080/00295639.2019.1665459
Adaptive Reweighted Variance Estimation for Monte Carlo Eigenvalue Simulations
Lei Jin, Kaushik Banerjee
Nuclear Science and Engineering | Volume 194 | Number 3 | March 2020 | Pages 190-206
Technical Paper | doi.org/10.1080/00295639.2019.1678104
Spectroscopy of High-Intensity Bremsstrahlung Using Compton Recoiled Electrons
C. V. Midhun, M. M. Musthafa, Shaima Akbar, Swapna Lilly Cyriac, S. Sajeev, Antony Joseph, K. C. Jagadeesan, S. V. Suryanarayana, S. Ganesan
Nuclear Science and Engineering | Volume 194 | Number 3 | March 2020 | Pages 207-212
Technical Paper | doi.org/10.1080/00295639.2019.1681210
Ensuring Criticality Safety of vSMR Core During Transport Based on Its Temperature Reactivity
Rei Kimura, Kazuhito Asano
Nuclear Science and Engineering | Volume 194 | Number 3 | March 2020 | Pages 213-220
Technical Paper | doi.org/10.1080/00295639.2019.1685352
Validation of Unresolved Neutron Resonance Parameters Using a Thick-Sample Transmission Measurement
Jesse M. Brown, R. C. Block, A. Youmans, H. Choun, A. Ney, E. Blain, D. P. Barry, M. J. Rapp, Y. Danon
Nuclear Science and Engineering | Volume 194 | Number 3 | March 2020 | Pages 221-231
Technical Paper | doi.org/10.1080/00295639.2019.1688087
A Comparison Between the Embedded Self-Shielding Method and the Enhanced Neutron Current Method Based on the Equivalent Pin Cell Model on the Irregular Fuel Lattice Problem
Qian Zhang, Liang Liang, Qiang Zhao, Zhijian Zhang, Hongchun Wu, Liangzhi Cao
Nuclear Science and Engineering | Volume 194 | Number 3 | March 2020 | Pages 232-247
Technical Note | doi.org/10.1080/00295639.2019.1664146
Integrated State Awareness Through Secure Embedded Intelligence in Nuclear Systems: Opportunities and Implications
Humberto E. Garcia, Steven E. Aumeier, Ahmad Y. Al-Rashdan
Nuclear Science and Engineering | Volume 194 | Number 4 | April 2020 | Pages 249-269
Technical Paper | doi.org/10.1080/00295639.2019.1698237
Neutronic Analysis to Replace Cobalt Radioisotope Facility by Iridium Radioisotope Facility at ETRR-2
Mohamed A. Elsaied, Alya A. Badawi, Nader M. A. Mohamed, Ahmed El Saghir, Asmaa G. Abo Elnour
Nuclear Science and Engineering | Volume 194 | Number 4 | April 2020 | Pages 270-279
Technical Paper | doi.org/10.1080/00295639.2019.1698238
On-The-Fly Prediction of Macroscopic Cross-Section Spatial Response to TH Perturbations Through Transfer Functions: Theory and First Results
Stefano Terlizzi, Dan Kotlyar
Nuclear Science and Engineering | Volume 194 | Number 4 | April 2020 | Pages 280-296
Technical Paper | doi.org/10.1080/00295639.2019.1698239
Real Variance Estimation in Monte Carlo Criticality Calculation Accelerated by p-CMFD Feedback Using Spectral Analysis Method
HyeonTae Kim, YuGwon Jo, Yonghee Kim
Nuclear Science and Engineering | Volume 194 | Number 4 | April 2020 | Pages 297-307
Technical Paper | doi.org/10.1080/00295639.2019.1698240
Application of Neutron Multiplicity Counting Experiments to Optimal Cross-Section Adjustments
Alexander R. Clark, John Mattingly, Jeffrey A. Favorite
Nuclear Science and Engineering | Volume 194 | Number 4 | April 2020 | Pages 308-333
Technical Paper | doi.org/10.1080/00295639.2019.1698267
A High-Precision Tagged Neutron n-p Scattering Measurement at 14.9 MeV
N. V. Kornilov, S. M. Grimes, T. N. Massey, C. E. Brient, D. E. Carter, J. E. O’Donnell, K. W. Cooper, A. D. Carlson, F. B. Bateman, C. R. Heimbach, N. Boukharouba
Nuclear Science and Engineering | Volume 194 | Number 5 | May 2020 | Pages 335-349
Technical Paper | doi.org/10.1080/00295639.2019.1702408
Single Scattering Adjoint Monte Carlo Electron Transport in FRENSIE
Luke J. Kersting, Alex Robinson, Eli Moll, Philip Britt, Lewis Gross, Douglass Henderson
Nuclear Science and Engineering | Volume 194 | Number 5 | May 2020 | Pages 350-372
Technical Paper | doi.org/10.1080/00295639.2019.1701344
Simulation of Multiple-Component Charged Aerosol Evolution
Fernando De La Torre Aguilar, Sudarshan K. Loyalka
Nuclear Science and Engineering | Volume 194 | Number 5 | May 2020 | Pages 373-404
Technical Paper | doi.org/10.1080/00295639.2019.1707153
Evaluation of Discharged Fuel in Preproposed Breed-and-Burn Reactors from Proliferation, Decay Heat, and Radiotoxicity Aspects
Kazuki Kuwagaki, Jun Nishiyama, Toru Obara
Nuclear Science and Engineering | Volume 194 | Number 5 | May 2020 | Pages 405-413
Technical Note | doi.org/10.1080/00295639.2019.1706322
Empiric Calculation of the Power Increase Caused by Fuel Assembly Bowing in Siemens/KWU-PWR
Jonas Berger, Alexander Mühle, Kai-Martin Haendel
Nuclear Science and Engineering | Volume 194 | Number 6 | June 2020 | Pages 415-421
Technical Paper | doi.org/10.1080/00295639.2019.1705656
Judgment on Convergence-in-Distribution of Monte Carlo Tallies Under Autocorrelation
Taro Ueki
Nuclear Science and Engineering | Volume 194 | Number 6 | June 2020 | Pages 422-432
Technical Paper | doi.org/10.1080/00295639.2019.1710418
LQG/LTR Controller Design Based on Improved SFACC for the PWR Reactor Power Control System
Jiashuang Wan, Pengfei Wang
Nuclear Science and Engineering | Volume 194 | Number 6 | June 2020 | Pages 433-446
Technical Paper | doi.org/10.1080/00295639.2019.1710419
An Optimization Algorithm Based on Artificial Potential Field and Particle Swarm Optimization to Avoid Radiation Exposure Under Radioactive Environment
Mengkun Li, Guanxiang Wei, Zhihui Xu, Jun Wang, Ming Yang
Nuclear Science and Engineering | Volume 194 | Number 6 | June 2020 | Pages 447-461
Technical Paper | doi.org/10.1080/00295639.2019.1710975
Experimental Investigation of FCCI Using Diffusion Couple Test Between UZr Fuel with Sb Additive and Cladding
Weiqian Zhuo, Yi Xie, Michael T. Benson, Qiufeng Yang, Robert D. Mariani, Jinsuo Zhang
Nuclear Science and Engineering | Volume 194 | Number 6 | June 2020 | Pages 462-476
Technical Paper | doi.org/10.1080/00295639.2020.1713656
Impact of Various Parameters on Convergence Performance of CMFD Acceleration for MOC in Multigroup Heterogeneous Geometry
Yoshiki Oshima, Tomohiro Endo, Akio Yamamoto, Yasuhiro Kodama, Yasunori Ohoka, Hiroaki Nagano
Nuclear Science and Engineering | Volume 194 | Number 6 | June 2020 | Pages 477-491
Technical Paper | doi.org/10.1080/00295639.2020.1722512
Reactivity Feedback Effect on Supercritical Transient Analysis of Fuel Debris
Kodai Fukuda, Jun Nishiyama, Toru Obara
Nuclear Science and Engineering | Volume 194 | Number 7 | July 2020 | Pages 493-507
Technical Paper | doi.org/10.1080/00295639.2020.1743580
Consistent Transport Transient Solvers of the High-Fidelity Transport Code PROTEUS-MOC
Albert Hsieh, Guangchun Zhang, Won Sik Yang
Nuclear Science and Engineering | Volume 194 | Number 7 | July 2020 | Pages 508-540
Technical Paper | doi.org/10.1080/00295639.2020.1746619
Identification of Working Conditions in Secondary Loop of Nuclear Power Plant Based on Improved Multiple PCA Modeling
Yunfeng Zhang, Xiangshun Li, Lin Cai
Nuclear Science and Engineering | Volume 194 | Number 7 | July 2020 | Pages 541-553
Technical Paper | doi.org/10.1080/00295639.2020.1751526
A Linear Prolongating Coarse Mesh Finite Difference Acceleration of Discrete Ordinate Neutron Transport Calculation Based on Discontinuous Galerkin Finite Element Method
Yimeng Chan, Sicong Xiao
Nuclear Science and Engineering | Volume 194 | Number 7 | July 2020 | Pages 554-571
Technical Paper | doi.org/10.1080/00295639.2020.1752045
Modeling and Estimation of Nuclear Reactor Performance Using Fractional Neutron Point Kinetics with Temperature Effect and Xenon Poisoning
K. Rady, A. A. Abouelsoud, S. A. Kotb, M. M. El Metwally
Nuclear Science and Engineering | Volume 194 | Number 7 | July 2020 | Pages 572-582
Technical Paper | doi.org/10.1080/00295639.2020.1755808
Velocity Field and Scalar Field Measurements of Turbulent Buoyant Round Jets in a Two-Layer Stratified Environment
Sunming Qin, Victor Petrov, Annalisa Manera
Nuclear Science and Engineering | Volume 194 | Number 8-9 | August-September 2020 | Pages 583-597
Technical Paper | doi.org/10.1080/00295639.2020.1755805
Validation of the Interfacial Area Transport Equation Coupled with the Void Transport Equation for Prediction of Flashing Flows
Zhiee Jhia Ooi, Vineet Kumar, Caleb S. Brooks
Nuclear Science and Engineering | Volume 194 | Number 8-9 | August-September 2020 | Pages 598-619
Technical Paper | doi.org/10.1080/00295639.2020.1732123
Critical Heat Flux Model for Vertical Annular Mist Flow Conditions in a Rod Bundle
José N. Reyes, Jr.
Nuclear Science and Engineering | Volume 194 | Number 8-9 | August-September 2020 | Pages 620-632
Technical Paper | doi.org/10.1080/00295639.2020.1721236
A Multiscale and Multiphysics PWR Safety Analysis at a Subchannel Scale
H. Y. Yoon, I. K. Park, J. R. Lee, S. J. Lee, Y. J. Cho, S. J. Do, H. K. Cho, J. J. Jeong
Nuclear Science and Engineering | Volume 194 | Number 8-9 | August-September 2020 | Pages 633-649
Technical Paper | doi.org/10.1080/00295639.2020.1727698
Reynolds-Averaged Turbulence Modeling Using Deep Learning with Local Flow Features: An Empirical Approach
Chih-Wei Chang, Jun Fang, Nam T. Dinh
Nuclear Science and Engineering | Volume 194 | Number 8-9 | August-September 2020 | Pages 650-664
Technical Paper | doi.org/10.1080/00295639.2020.1712928
Density Wave Instability Verification of CFD Two-Fluid Model
S. L. Sharma, J. R. Buchanan, M. A. Lopez de Bertodano
Nuclear Science and Engineering | Volume 194 | Number 8-9 | August-September 2020 | Pages 665-675
Technical Paper | doi.org/10.1080/00295639.2020.1744406
Annular Flow Simulation Supported by Iterative In-Memory Mesh Adaptation
Jun Fang, Meredith K. Purser, Cameron Smith, Ramesh Balakrishnan, Igor A. Bolotnov, Kenneth E. Jansen
Nuclear Science and Engineering | Volume 194 | Number 8-9 | August-September 2020 | Pages 676-689
Technical Paper | doi.org/10.1080/00295639.2020.1743577
Progress Toward Simulating Departure from Nucleate Boiling at High-Pressure Applications with Selected Wall Boiling Closures
Seung Jun Kim, Russell C. Johns, Junsoo Yoo, Emilio Baglietto
Nuclear Science and Engineering | Volume 194 | Number 8-9 | August-September 2020 | Pages 690-707
Technical Paper | doi.org/10.1080/00295639.2020.1743579
Exploring Two-Phase Flow Regime Transition Mechanisms Using High-Resolution Virtual Experiments
Matthew D. Zimmer, Igor A. Bolotnov
Nuclear Science and Engineering | Volume 194 | Number 8-9 | August-September 2020 | Pages 708-720
Technical Paper | doi.org/10.1080/00295639.2020.1722543
SAPIUM: A Generic Framework for a Practical and Transparent Quantification of Thermal-Hydraulic Code Model Input Uncertainty
Jean Baccou, Jinzhao Zhang, Philippe Fillion, Guillaume Damblin, Alessandro Petruzzi, Rafael Mendizábal, Francesc Reventos, Tomasz Skorek, Mathieu Couplet, Bertrand Iooss, Deog-Yeon Oh, Takeshi Takeda, Nils Sandberg
Nuclear Science and Engineering | Volume 194 | Number 8-9 | August-September 2020 | Pages 721-736
Technical Paper | doi.org/10.1080/00295639.2020.1759310
Validation and Uncertainty Quantification for Two-Phase Natural Circulation Flows Using TRACE Code
Katarzyna Borowiec, Tomasz Kozlowski, Caleb S. Brooks
Nuclear Science and Engineering | Volume 194 | Number 8-9 | August-September 2020 | Pages 737-747
Technical Paper | doi.org/10.1080/00295639.2020.1713671
Risk-Informed Safety Analysis for Accident Tolerant Fuels
Carlo Parisi, Zhegang Ma, Diego Mandelli, Nolan Anderson, Hongbin Zhang
Nuclear Science and Engineering | Volume 194 | Number 8-9 | August-September 2020 | Pages 748-770
Technical Paper | doi.org/10.1080/00295639.2020.1732699
EDF MAAP5.04 LOCA Transient Simulation Improvements
Jeremy Bittan
Nuclear Science and Engineering | Volume 194 | Number 8-9 | August-September 2020 | Pages 771-781
Technical Paper | doi.org/10.1080/00295639.2020.1743576
Advancing Radiative Heat Transfer Modeling in High-Temperature Liquid Salts
Carolyn Coyle, Emilio Baglietto, Charles Forsberg
Nuclear Science and Engineering | Volume 194 | Number 8-9 | August-September 2020 | Pages 782-792
Technical Paper | doi.org/10.1080/00295639.2020.1723993
Scaling Methodology for Integral Effects Tests in Support of Fluoride Salt–Cooled High-Temperature Reactor Technology
Nicolas Zweibaum, Edward Blandford, Craig Gerardi, Per Peterson
Nuclear Science and Engineering | Volume 194 | Number 8-9 | August-September 2020 | Pages 793-811
Technical Paper | doi.org/10.1080/00295639.2019.1710976
Advanced Studies and Statistical Treatment for Sodium-Cooled Fast Reactor Pin Failures During Unprotected Transient Overpower Accident
N. Marie, K. Herbreteau, A. Marrel, F. Bertrand, A. Bachrata
Nuclear Science and Engineering | Volume 194 | Number 8-9 | August-September 2020 | Pages 812-824
Technical Note | doi.org/10.1080/00295639.2020.1722542
Scaling Analysis of Thermal-Hydraulic Integral Systems: Insights from Practical Applications and Recent Advancements
Cesare Frepoli
Nuclear Science and Engineering | Volume 194 | Number 8-9 | August-September 2020 | Pages 825-832
Technical Note | doi.org/10.1080/00295639.2020.1753419
Reduced-Order Modeling of Nuclear Reactor Kinetics Using Proper Generalized Decomposition
Anthony L. Alberti, Todd S. Palmer
Nuclear Science and Engineering | Volume 194 | Number 10 | October 2020 | Pages 837-858
Technical Paper | doi.org/10.1080/00295639.2020.1758482
A Multiscale Approach Simulating Generic Pool Boiling
T. Höhne, D. Lucas
Nuclear Science and Engineering | Volume 194 | Number 10 | October 2020 | Pages 859-872
Technical Paper | doi.org/10.1080/00295639.2020.1764265
Thermal Upscattering Acceleration Schemes for Parallel Transport Sweeps
Milan Hanus, Jean C. Ragusa
Nuclear Science and Engineering | Volume 194 | Number 10 | October 2020 | Pages 873-893
Technical Paper | doi.org/10.1080/00295639.2020.1767436
An Integral Experiment on Polyethylene Using Radiative Capture in Indium Foils in a High Flux D-D Neutron Generator
Nnaemeka Nnamani, Karl Van Bibber, Lee A. Bernstein, Jasmina L. Vujic, Jonathan T. Morrell, Jon C. Batchelder, Mauricio Ayllon
Nuclear Science and Engineering | Volume 194 | Number 10 | October 2020 | Pages 894-902
Technical Paper | doi.org/10.1080/00295639.2020.1769964
Model Error Estimation for the Simplified PN Radiation Transport Equations
Yunhuang Zhang, Jean C. Ragusa, Jim E. Morel
Nuclear Science and Engineering | Volume 194 | Number 10 | October 2020 | Pages 903-926
Technical Paper | doi.org/10.1080/00295639.2020.1771141
Mechanism of Fission Neutron Emission: New Experimental Arguments
N. V. Kornilov, S. M. Grimes
Nuclear Science and Engineering | Volume 194 | Number 10 | October 2020 | Pages 927-937
Technical Note | doi.org/10.1080/00295639.2020.1768779
Nonlinear Elimination Applied to Radiation Diffusion
Thomas A. Brunner, Terry S. Haut, Paul F. Nowak
Nuclear Science and Engineering | Volume 194 | Number 11 | November 2020 | Pages 939-951
Technical Paper | doi.org/10.1080/00295639.2020.1747262
Toward Asymptotic Diffusion Limit Preserving High-Order, Low-Order Method
H. Park
Nuclear Science and Engineering | Volume 194 | Number 11 | November 2020 | Pages 952-970
Technical Paper | doi.org/10.1080/00295639.2020.1769390
Ray Effect Mitigation for the Discrete Ordinates Method Using Artificial Scattering
Martin Frank, Jonas Kusch, Thomas Camminady, Cory D. Hauck
Nuclear Science and Engineering | Volume 194 | Number 11 | November 2020 | Pages 971-988
Technical Paper | doi.org/10.1080/00295639.2020.1730665
Parallel Approximate Ideal Restriction Multigrid for Solving the SN Transport Equations
Joshua Hanophy, Ben S. Southworth, Ruipeng Li, Tom Manteuffel, Jim Morel
Nuclear Science and Engineering | Volume 194 | Number 11 | November 2020 | Pages 989-1008
Technical Paper | doi.org/10.1080/00295639.2020.1747263
Threadsafe Dynamic Neighbor Lists for Monte Carlo Ray Tracing
Sterling M. Harper, Paul K. Romano, Benoit Forget, Kord S. Smith
Nuclear Science and Engineering | Volume 194 | Number 11 | November 2020 | Pages 1009-1015
Technical Paper | doi.org/10.1080/00295639.2020.1719765
serpentTools: A Python Package for Expediting Analysis with Serpent
Andrew E. Johnson, Dan Kotlyar, Stefano Terlizzi, Gavin Ridley
Nuclear Science and Engineering | Volume 194 | Number 11 | November 2020 | Pages 1016-1024
Technical Paper | doi.org/10.1080/00295639.2020.1723992
Multigroup Constant Calculation with Static α-Eigenvalue Monte Carlo for Time-Dependent Neutron Transport Simulations
Ilham Variansyah, Benjamin R. Betzler, William R. Martin
Nuclear Science and Engineering | Volume 194 | Number 11 | November 2020 | Pages 1025-1043
Technical Paper | doi.org/10.1080/00295639.2020.1743578
Generalized Equivalence Theory Used with Spatially Linear Sources in the Method of Characteristics for Neutron Transport
Guillaume Giudicelli, Kord Smith, Benoit Forget
Nuclear Science and Engineering | Volume 194 | Number 11 | November 2020 | Pages 1044-1055
Technical Paper | doi.org/10.1080/00295639.2020.1765606
Assessment of nTRACER and PARCS Performance for VVER Configurations
Marianna Papadionysiou, Kim Seongchan, Mathieu Hursin, Alexander Vasiliev, Hakim Ferroukhi, Andreas Pautz, Han Gyu Joo
Nuclear Science and Engineering | Volume 194 | Number 11 | November 2020 | Pages 1056-1066
Technical Paper | doi.org/10.1080/00295639.2020.1753418
Neutronic Simulation of Fuel Assembly Vibrations in a Nuclear Reactor
A. Vidal-Ferràndiz, A. Carreño, D. Ginestar, C. Demazière, G. Verdú
Nuclear Science and Engineering | Volume 194 | Number 11 | November 2020 | Pages 1067-1078
Technical Paper | doi.org/10.1080/00295639.2020.1756617
Sensitivity and Uncertainty Analysis of Neutron Spectrum and DPA in a B&B Core
Chris Keckler, Massimiliano Fratoni, Ehud Greenspan
Nuclear Science and Engineering | Volume 194 | Number 11 | November 2020 | Pages 1079-1088
Technical Paper | doi.org/10.1080/00295639.2020.1715688
Data Assimilation Using Subcritical Measurement of Prompt Neutron Decay Constant
Tomohiro Endo, Akio Yamamoto
Nuclear Science and Engineering | Volume 194 | Number 11 | November 2020 | Pages 1089-1104
Technical Paper | doi.org/10.1080/00295639.2020.1720499
Optimized Separative Power of Hyperspeed Iguassu Gas Centrifuge: Dependence on the Rotor Diameter and Velocity
Sergey V. Bogovalov, Vladimir D. Borman, Ivan V. Tronin, Vladimir N. Tronin
Nuclear Science and Engineering | Volume 194 | Number 12 | December 2020 | Pages 1105-1115
Technical Paper | doi.org/10.1080/00295639.2020.1774229
Neutron Generation Time in Highly-Enriched Uranium Core at Kyoto University Critical Assembly
Cheol Ho Pyeon, Masao Yamanaka, Tomohiro Endo, Go Chiba, Willem F. G Van Rooijen, Kenichi Watanabe
Nuclear Science and Engineering | Volume 194 | Number 12 | December 2020 | Pages 1116-1127
Technical Paper | doi.org/10.1080/00295639.2020.1774230
Burnup Performance of CANDLE Burning Reactor Using Sodium Coolant
Hoang Hai Nguyen, Jun Nishiyama, Toru Obara
Nuclear Science and Engineering | Volume 194 | Number 12 | December 2020 | Pages 1128-1142
Technical Paper | doi.org/10.1080/00295639.2020.1775433
Solving Burnup Equations by Numerical Inversion of the Laplace Transform Using Padé Rational Approximation
Shaopeng Xia, Maosong Cheng, Zhimin Dai
Nuclear Science and Engineering | Volume 194 | Number 12 | December 2020 | Pages 1143-1161
Technical Paper | doi.org/10.1080/00295639.2020.1776057
Wall-Climbing Robot with Active Sealing for Radiation Safety of Nuclear Power Plants
Daewon Kim, Yun-Sam Kim, Kyoungyong Noh, Misuk Jang, Seoungrae Kim
Nuclear Science and Engineering | Volume 194 | Number 12 | December 2020 | Pages 1162-1174
Technical Paper | doi.org/10.1080/00295639.2020.1777023
Nonmatching Discontinuous Cartesian Grid Algorithm Based on the Multilevel Octree Architecture for Discrete Ordinates Transport Calculation
Cong Liu, Bin Zhang, Liang Zhang, Yixue Chen
Nuclear Science and Engineering | Volume 194 | Number 12 | December 2020 | Pages 1175-1201
Technical Paper | doi.org/10.1080/00295639.2020.1780842
