ANS / Publications / Journals / Nuclear Science and Engineering

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2020.1769964

Model Error Estimation for the Simplified P_N 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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2020.1730665

Parallel Approximate Ideal Restriction Multigrid for Solving the S_N 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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2020.1780842