JournalTOCs

Nuclear Science and Engineering
Journal Prestige (SJR): 0.92

Citation Impact (citeScore): 1
Number of Followers: 7

Hybrid journal * Containing 24 Open Access article(s) in this issue *
ISSN (Print) 0029-5639 - ISSN (Online) 1943-748X
Published by Taylor and Francis

[2652 journals]

Asymptotic Expansion of the Angular Flux Applied to Discrete-Ordinates
Source Iterations in Lattice Depletion Calculations
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  Authors: E. Masiello, F. Filiciotto, S. Lapuerta-Cochet, R. Lenain
  Pages: 1 - 21
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-13T01:43:39Z
  DOI: 10.1080/00295639.2023.2175583
Experimental Estimation of the Kinetic Parameters of MINERVE Zero Power
Reactor
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  Authors: Guy Shtotland, Assaf Kolin, Benoit Geslot, Patrick Blaise, Nir Kastin
  Pages: 1 - 10
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-13T01:41:05Z
  DOI: 10.1080/00295639.2023.2174761
Void Reactivity in Lead and Bismuth Sample Reactivity Experiments at Kyoto
University Critical Assembly
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  Authors: Cheol Ho Pyeon, Ryota Katano, Akito Oizumi, Masahiro Fukushima
  Pages: 1 - 18
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-13T01:40:16Z
  DOI: 10.1080/00295639.2023.2172311
Establishment of Control Room Habitability Analysis Methodology
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  Authors: Anjun Jiao, David Ricks, Thomas Remick, Brian J. Hansen
  Pages: 1 - 10
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-13T01:38:30Z
  DOI: 10.1080/00295639.2023.2171274
Second Target Station Bunker Shielding with Populated and Unpopulated
Neutron Beamlines: Preliminary Design
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  Authors: Thomas M. Miller, Paul Mueller, Kumar Mohindroo, Igor Remec
  Pages: 1 - 16
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-10T08:28:06Z
  DOI: 10.1080/00295639.2023.2181027
Influence of Particle Beam and Accelerator Type on ADS Efficiency
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  Authors: M. Paraipan, V. M. Javadova, S. I. Tyutyunnikov
  Pages: 1 - 12
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-10T08:27:17Z
  DOI: 10.1080/00295639.2023.2175582
Acceleration Waves in Cylindrical Shrinking Gas Bubbles
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  Authors: Francesca Brini, Leonardo Seccia
  Pages: 1 - 16
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-09T02:28:47Z
  DOI: 10.1080/00295639.2023.2166754
Scaling, Passive Systems, and the AP-1000
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  Authors: F. D’Auria
  Pages: 1 - 13
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-09T02:28:23Z
  DOI: 10.1080/00295639.2023.2178874
Space-Dependent Calculation of the Multiplicity Moments for Shells With
the Inclusion of Scattering
Open Access Article
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  Authors: Imre Pázsit, Victor Dykin, Flynn Darby
  Pages: 1 - 17
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-09T02:26:54Z
  DOI: 10.1080/00295639.2023.2178249
Improved Methods for Calculating the Neutron Diffusion Coefficient of
General Pebble Bed
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  Authors: Yutong Wen, Ding She, Lei Shi
  Pages: 1 - 15
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-09T02:16:56Z
  DOI: 10.1080/00295639.2023.2172312
Neutron Multiplicity Counting Distribution Reconstruction from Moments
Using Meixner Polynomial Expansion and N-Forked Branching Approximations
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  Authors: Philippe Humbert
  Pages: 1 - 17
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-08T07:35:56Z
  DOI: 10.1080/00295639.2022.2162304
On the Effect of Scalar Flux Weighting of Linearly Anisotropic Scattering
Matrices in Higher-Order Transport Calculations
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  Authors: Zoltán István Böröczki, Boglárka Babcsány, János Endre Maróti, Máté Szieberth
  Pages: 1 - 19
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-08T07:35:40Z
  DOI: 10.1080/00295639.2023.2167469
Development of a 3D APOLLO3® Neutron Deterministic Calculation Scheme for
the CABRI Experimental Reactor
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  Authors: Tommy Coissieux, Julien Politello, Claire Vaglio-Gaudard, Karim Ammar
  Pages: 1 - 16
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-08T02:02:58Z
  DOI: 10.1080/00295639.2023.2167471
A New Approach for NaI(Tl) Detector Efficiency Calibration Using 41Ar
Radionuclide for Air Exhaust Systems
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  Authors: Mahsa Farasat, Federico Zagni, Lorenzo Pompignoli, G. A. Pablo Cirrone, Ulrich W. Scherer, Lidia Strigari, Domiziano Mostacci
  Pages: 1 - 10
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-02T03:40:39Z
  DOI: 10.1080/00295639.2022.2164148
Preliminary Neutronics Design and Analysis of the Fast Modular Reactor
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  Authors: Hangbok Choi, Darrin Leer, Matthew Virgen, Oscar Gutierrez, John Bolin
  Pages: 1 - 11
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-02T03:39:39Z
  DOI: 10.1080/00295639.2022.2158707
Development of Experimental Core Configurations to Clarify keff Variations
by Nonuniform Core Configurations
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  Authors: Satoshi Gunji, Shouhei Araki, Kenya Suyama
  Pages: 1 - 13
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-02T03:39:31Z
  DOI: 10.1080/00295639.2022.2164151
Concept Descriptions for the VTR Rabbit System and Driver Fuel Test
Assemblies
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  Authors: Sean M. McDeavitt, David Wootan, Mark Kimber, Karen Vierow Kirkland, Luis H. Ortega, Delia Perez-Nunez, Pavel Tsvetkov, Jason Hearne, Abdullah Weiss, Saleem Drera, Nicolas E. Woolstenhulme
  Pages: 1 - 13
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-01T04:01:13Z
  DOI: 10.1080/00295639.2023.2166765
Design and Development of the 200-kW Beam Dump
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  Authors: Huan Jia, Haihua Niu, Han-Jie Cai, Chenzhang Yuan, Xunchao Zhang, Yuanshuai Qin, Hongming Xie, Baifan Wang, Peng Zhang, Yuxuan Huang, Tieming Zhu, Tianji Peng, Weilong Chen, Qingwei Chu, Jianqiang Wu, Shenghu Zhang, Xiang Li, Duanyang Jia, Bin Zhang, Yuan He, Hongwei Zhao, Wenlong Zhan
  Pages: 1 - 10
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-03-01T03:57:12Z
  DOI: 10.1080/00295639.2022.2164149
141Pr(α,x): New Cross-Section Data With Special Reference to 140Nd
Production for Medicine
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  Authors: Ekaterina Sergeevna Kormazeva, Anastasia Romanovna Kulakova, Vladimir Ilyich Novikov, Ramiz Avtandilovich Aliev
  Pages: 1 - 12
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-28T09:34:04Z
  DOI: 10.1080/00295639.2022.2162303
Uncertainty Propagation in UAM Time-Dependent Neutronics PWR Studies
Open Access Article
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  Authors: M. D. Tucker, D. R. Novog
  Pages: 1 - 26
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-24T04:52:13Z
  DOI: 10.1080/00295639.2022.2160612
Benchmark of Neutron Thermalization in Graphite Using a Pulsed
Slowing-Down-Time Experiment
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  Authors: Eunji Lee, N. Colby Fleming, Ayman I. Hawari
  Pages: 1 - 10
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-24T04:51:42Z
  DOI: 10.1080/00295639.2022.2162789
Source Nuclide Density First-Order and Second-Order Sensitivities in Monte
Carlo Codes
Open Access Article
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  Authors: Jeffrey A. Favorite
  Pages: 1 - 13
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-23T05:30:03Z
  DOI: 10.1080/00295639.2022.2161279
Design of a Fast Molten Salt Reactor for Space Nuclear Electric Propulsion
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  Authors: F. Quinteros, P. Rubiolo, V. Ghetta, J. Giraud, N. Capellan
  Pages: 1 - 16
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-16T07:37:13Z
  DOI: 10.1080/00295639.2023.2167470
Coupled Monte Carlo Transport and Conjugate Heat Transfer for Wire-Wrapped
Bundles Within the MOOSE Framework
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  Authors: A. J. Novak, P. Shriwise, P. K. Romano, R. Rahaman, E. Merzari, D. Gaston
  Pages: 1 - 24
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-16T07:36:18Z
  DOI: 10.1080/00295639.2022.2158715
Multigroup Neutron Transport Using a Collision-Based Hybrid Method
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  Authors: Ben Whewell, Ryan G. McClarren, Cory D. Hauck, Minwoo Shin
  Pages: 1 - 20
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-16T07:35:41Z
  DOI: 10.1080/00295639.2022.2154119
Feasibility of Using Poisons to Suppress the Positive Temperature
Reactivity Coefficient in Hydride-Moderated Reactors
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  Authors: Vedant K. Mehta, Zachary A. Miller, Dasari V. Rao
  Pages: 1 - 15
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-16T07:34:03Z
  DOI: 10.1080/00295639.2022.2164150
Transition Core Modeling for Extended-Enrichment Accident-Tolerant Fuels
in Light Water Reactors Using PARCS/Polaris
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  Authors: Muhammad Rizki Oktavian, Ugur Mertyurek, Yunlin Xu
  Pages: 1 - 14
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-16T07:32:20Z
  DOI: 10.1080/00295639.2022.2162790
Neutronic Evaluation and Optimization of the Centrifugal Nuclear Thermal
Rocket Concept
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  Authors: William J. Walters
  Pages: 1 - 11
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-13T08:55:06Z
  DOI: 10.1080/00295639.2022.2161805
Evaluating Quantities of Interest Other Than Nuclide Densities in the
Bateman Equations
Open Access Article
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  Authors: Olin W. Calvin, Micah D. Gale, Sebastian Schunert
  Pages: 1 - 17
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-13T08:55:05Z
  DOI: 10.1080/00295639.2022.2161802
Monte Carlo Study of an Electron-Based Neutron Source for Bragg Edge
Imaging
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  Authors: Mahdi Bakhtiari, Nam-Suk Jung, Wooyong Um, Hee-Seock Lee
  Pages: 1 - 15
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-13T08:54:43Z
  DOI: 10.1080/00295639.2022.2162791
An Efficient High-to-Low Iterative Method for Light Water Reactor Analysis
Based on NEAMS Tools
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  Authors: Kan Ni, Jason Hou
  Pages: 1 - 17
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-13T08:46:05Z
  DOI: 10.1080/00295639.2022.2158706
Radiation Dose Assessment of Tritium Released from the Thorium Molten Salt
Reactor
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  Authors: Wenyu Cheng, Jie Liang, Mingjun Zhang, Fei Wei, Jinglin Li, Xiaochong Xue, Youshi Zeng, Ke Deng, Qin Zhang, Wei Liu
  Pages: 1 - 11
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-13T08:45:04Z
  DOI: 10.1080/00295639.2022.2158020
Two-Phase Turbulent Kinetic Energy Budget Computation in Co-Current Taylor
Bubble Flow
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  Authors: E. M. A. Frederix, S. Tajfirooz, J. A. Hopman, J. Fang, E. Merzari, E. M. J. Komen
  Pages: 1 - 17
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-13T08:45:02Z
  DOI: 10.1080/00295639.2022.2141517
Physics-Informed Neural Networks for 1-D Steady-State
Diffusion-Advection-Reaction Equations
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  Authors: Laura Laghi, Enrico Schiassi, Mario De Florio, Roberto Furfaro, Domiziano Mostacci
  Pages: 1 - 31
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-09T05:29:42Z
  DOI: 10.1080/00295639.2022.2160604
A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC
Fusion Reactor Design
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  Authors: Alex Aimetta, Nicolò Abrate, Sandra Dulla, Antonio Froio
  Pages: 1 - 25
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-09T05:29:13Z
  DOI: 10.1080/00295639.2022.2153638
State of the Art on Doppler Broadening: Modern Developments on the Fuel
Temperature Coefficient
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  Authors: David Friant, David Bernard, Patrick Blaise
  Pages: 1 - 16
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-09T05:28:33Z
  DOI: 10.1080/00295639.2022.2158679
Measurements of Droplet Size and Velocity Distributions During Rod Bundle
Core Reflood
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  Authors: Grant R. Garrett, Brian R. Lowery, Molly K. Hanson, Douglas J. Miller, Turki Almudhhi, Fan-Bill Cheung, Stephen M. Bajorek, Kirk Tien, Chris L. Hoxie
  Pages: 1 - 25
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-09T05:28:28Z
  DOI: 10.1080/00295639.2022.2157189
MOOSE Reactor Module: An Open-Source Capability for Meshing Nuclear
Reactor Geometries
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  Authors: Emily Shemon, Yinbin Miao, Shikhar Kumar, Kun Mo, Yeon Sang Jung, Aaron Oaks, Scott Richards, Guillaume Giudicelli, Logan Harbour, Roy Stogner
  Pages: 1 - 25
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-09T05:28:13Z
  DOI: 10.1080/00295639.2022.2149231
Enhancing Monte Carlo Workflows for Nuclear Reactor Analysis with
Metamodel-Driven Modeling
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  Authors: Peter J. Kowal, Camden E. Blake, Kurt A. Dominesey, Robert A. Lefebvre, Forrest B. Brown, Wei Ji
  Pages: 1 - 21
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-09T05:28:04Z
  DOI: 10.1080/00295639.2022.2153617
Research and Application of the Rehomogenization Method for PWR Core
Neutron Physics Simulation
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  Authors: Chenghui Wan, Wenchang Dong, Lin Guo, Jiahe Bai
  Pages: 1 - 13
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-03T07:14:29Z
  DOI: 10.1080/00295639.2022.2158704
Analysis of Major Benchmark Uncertainties for Fast Metal Assemblies in the
ICSBEP Handbook
Open Access Article
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  Authors: Theresa Cutler, Kelsey Amundson, Jesson Hutchinson, Nick Thompson
  Pages: 1 - 25
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-03T07:14:29Z
  DOI: 10.1080/00295639.2022.2159293
Development and Validation of Thermal-Mechanical Creep Failure Module for
Reactor Pressure Vessel Lower Head
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  Authors: Hao Yang, Bin Zhang, Pengcheng Gao, Runze Zhai, Jianqiang Shan
  Pages: 1 - 18
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-02-03T07:14:23Z
  DOI: 10.1080/00295639.2022.2158676
Spherical Harmonics and Discontinuous Galerkin Finite Element Methods for
the Three-Dimensional Neutron Transport Equation: Application to Core and
Lattice Calculation
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Deep Learning for Multigroup Cross-Section Representation in Two-Step Core
Calculations
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An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering:
Part III. Uncertainty Propagation and Multigroup Covariance Matrices
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Demonstrating Computational Equivalence Between Continuous and Discrete
Adjoint Methods by Calculating Time-Dependent Adjoint Solutions with
Neutron Diffusion Models
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Multi-Output Gaussian Processes for Inverse Uncertainty Quantification in
Neutron Noise Analysis
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Generation IV Nuclear Reactor: Coolant Materials in the Supercritical
State
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Impact of the Melt-Refining Process on the Performance of Sodium-Cooled
Rotational Fuel-Shuffling Breed-and-Burn Reactors
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Performance Testing of Person Passable Openings to Evaluate Accepted Risk
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EBR-II MOX Fuel Characterization Enabling ARES Phase I Testing
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Investigation of the Influence of TeO2 on the Elastic and Radiation
Shielding Capabilities of Phosphot-Tellurite Glasses Doped With Sm2O3
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Horizontal Split-Table Conceptual Design to Support Advanced Reactor
Validation Needs
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Mixcoatl Software (Part 1): Coupled Thermal Physics and Mechanics for
Efficient Engineering Design
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Scoping Studies for a Lead-Lithium-Cooled, Minor-Actinide-Burning,
Fission-Fusion Hybrid Reactor Design
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High-Performance and High-Fidelity GPU Based Monte Carlo Solutions to the
BEAVRS Benchmark
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Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced
Fission of 245Cm
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The Virtual Test Bed (VTB) Repository: A Library of Reference Reactor
Models Using NEAMS Tools
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  Authors: Guillaume L. Giudicelli, Abdalla Abou-Jaoude, April J. Novak, Ahmed Abdelhameed, Paolo Balestra, Lise Charlot, Jun Fang, Bo Feng, Thomas Folk, Ramiro Freile, Thomas Freyman, Derek Gaston, Logan Harbour, Thanh Hua, Wen Jiang, Nicolas Martin, Yinbin Miao, Jason Miller, Isaac Naupa, Dan O’Grady, David Reger, Emily Shemon, Nicolas Stauff, Mauricio Tano, Stefano Terlizzi, Samuel Walker, Cody Permann
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  Citation: Nuclear Science and Engineering
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Thermal-Hydraulic Investigation of Steady-State Single-Phase Natural
Circulation of an Integral PWR-Type SMR Test Rig (iPSTR)
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  Authors: Muhammad Ishaq, Muhammad Ilyas, Alam Nawaz Khan Wardag, Muhammad Zaman, Mansoor H. Inayat
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Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron Induced
Fission of 229Th
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  PubDate: 2023-01-23T02:08:42Z
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Influence of Quantum Oscillations in the Thermal Scattering Law of
Zirconium Carbide on Neutron Thermalization and Criticality
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Discrete-Time Bayesian Networks Applied to Flexible Coping Strategies of
Nuclear Power Plant Systems
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Thermal-Hydraulic Analysis of the AFIP-7 Irradiation Test in the Advanced
Test Reactor—Oxide Growth Prediction and Correlation
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Application of Accelerator Beam Dumps for Dark Matter Searches
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A Generalized Eigenvalue Formulation for Core-Design Applications
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  Authors: Nicolo’ Abrate, Sandra Dulla, Piero Ravetto, Paolo Saracco
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myMUSCLE, a New Multiphysics, Multiscale Simulation Coupling Environment
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  Authors: H. J. Uitslag-Doolaard, K. Zwijsen, F. Roelofs, M. M. Stempniewicz
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Analyses of Critical Hydrogen Enrichment in PWR Containment Compartments
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  Authors: E. Schmidt, N. Reinke, M. Freitag, M. Sonnenkalb
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A Quasi–Monte Carlo Method With Krylov Linear Solvers for Multigroup
Neutron Transport Simulations
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  Authors: Sam Pasmann, Ilham Variansyah, C. T. Kelley, Ryan McClarren
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State of the Art in Cyclotrons for Radionuclide Production in Biomedicine
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  Authors: Mario Marengo, Gianfranco Cicoria, Angelo Infantino, Sara Vichi, Federico Zagni, Domiziano Mostacci
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  PubDate: 2023-01-11T02:57:51Z
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Geometry Extension and Assemblywise Domain Decomposition of nTRACER for
Direct Whole-Core Calculation of VVERs
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  Authors: Seongchan Kim, Han Gyu Joo
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  PubDate: 2023-01-11T02:56:05Z
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Multiphysics Analysis System for Heat Pipe Cooled Micro Reactors Employing
PRAGMA-OpenFOAM-ANLHTP
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  Authors: Jaeuk Im, Myung Jin Jeong, Namjae Choi, Kyung Min Kim, Hyoung Kyu Cho, Han Gyu Joo
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  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-11T02:55:51Z
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Post-Neutron Mass Yield Distribution in the Thermal Neutron Induced
Fission of 233U
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  Authors: H. Naik, S. P. Dange, R. J. Singh, W. Jang
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  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-11T02:52:46Z
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Review of the Fluid Dynamics and Heat Transport Phenomena in Packed Pebble
Bed Nuclear Reactors
Open Access Article
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  Authors: Rahman S. Almusafir, Ahmed A. Jasim, Muthanna H. Al-Dahhan
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  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-10T01:40:23Z
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Wigner-Wilkins Neutron/Nucleus Scattering Kernel Quantum Mechanically
Derived
Open Access Article
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  Authors: J. A. Grzesik
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  PubDate: 2023-01-10T01:38:56Z
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Nonconforming Three-Dimensional Model for PWR Control Rod Movements
Without Homogenization and Cusping Effect
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  Authors: F. Filiciotto, E. Masiello, S. Cochet-Lapuerta, R. Lenain
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  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-09T03:23:12Z
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A Novel Core Design with Movable Moderator for a Fluoride
Salt–Cooled High-Temperature Reactor
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  Authors: Zuolong Zhu, Dean Wang, Valmor de Almeida, Charles Forsberg, Eugene Shwageraus
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  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-05T03:36:39Z
  DOI: 10.1080/00295639.2022.2146436
Study of Reactor Core Loading Monitoring at the GUINEVERE Facility
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  Authors: A. Bailly, J.-L. Lecouey, A. Billebaud, S. Chabod, A. Kochetkov, A. Krása, F.-R. Lecolley, G. Lehaut, N. Marie, N. Messaoudi, G. Vittiglio, J. Wagemans
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  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-05T02:40:30Z
  DOI: 10.1080/00295639.2022.2148813
Feynman-α Analysis Using BGO Gamma-Ray Detector in a University
Training and Research Reactor
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  Authors: Masaki Goto, Tadafumi Sano, Kunihiro Nakajima, Takashi Kanda, Atsushi Sakon, Kengo Hashimoto
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-22T07:12:15Z
  DOI: 10.1080/00295639.2022.2143707
Numerical Investigation on the Thermal-Hydraulic Characteristics near a
Corroded Lower Head of the Reactor Vessel During IVR-ERVC
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  Authors: Cheng Peng, Youya Song, Jian Deng, Sen Mao, Jiang Wu
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-21T04:37:56Z
  DOI: 10.1080/00295639.2022.2143208
Capability Extension of the High-Resolution Thermal-Hydraulic Code ESCOT
for Hexagonal Geometry Core Multiphysics Analysis
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  Authors: Jorge Gonzalez-Amoros, Marianna Papadionysiou, Seongchan Kim, Han Gyu Joo
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-21T04:36:07Z
  DOI: 10.1080/00295639.2022.2140577
Post-Neutron Mass Yield Distribution in the Thermal Neutron Induced
Fission of 235U
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  Authors: H. Naik, S. P. Dange, R. J. Singh, W. Jang
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-21T04:35:57Z
  DOI: 10.1080/00295639.2022.2133947
High-Fidelity Neutron Transport Solution of High Temperature Gas-Cooled
Reactor by Three-Dimensional Linear Source Method of Characteristics
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  Authors: Kaijie Zhu, Boran Kong, Han Zhang, Jiong Guo, Fu Li
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-16T02:34:54Z
  DOI: 10.1080/00295639.2022.2143706
Euler-Euler Model of Bubbly Flow Using Particle-Center-Averaging Method
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  Authors: Hongmei Lyu, Fabian Schlegel, Roland Rzehak, Dirk Lucas
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-16T02:32:09Z
  DOI: 10.1080/00295639.2022.2131344
Deep Subcriticality Determination Using the Source Jerk Integral Method in
the SALMON Program
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Pressurized Water Reactor Core Power Control Using BAS-RBF-PID Approach
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Computational Fluid Dynamics Analysis of an Open-Pool Nuclear Research
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Variance Reduction and Noise Source Sampling Techniques for Monte Carlo
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Numerical Simulation of Sub-cooled Flow Boiling in a Vertical Annulus
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Introduction of the Adding and Doubling Method for Solving Bateman
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Using a Random Forest Model to Choose Optimized Group Structures
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Variable Dynamic Mode Decomposition For Estimating Time Eigenvalues in
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Compensated Feed water Pump Control Analysis of Effect of Base-Load
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An Improved Dual Asymmetric Penalized Least Squares Baseline Correction
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OpenFOAM-Hybrid: A Morphology Adaptive Multifield Two-Fluid Model
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Core Concept of Small Rotational Fuel-Shuffling Breed-and-Burn Fast
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State-of-the-Art in Evaluation Approaches for Risk Assessment of Insider
Threats to Nuclear Facility Physical Protection Systems
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Convergence Properties of a Linear Diffusion-Acceleration Method for
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Physics-Informed Neural Network Method and Application to Nuclear Reactor
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Experimental Analysis of Fast-Transient Flow Boiling in Various Flow
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Investigation of the Inhomogeneous Mechanical and Crack Driving Force of
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LQG/LTR Controller Design for Power Control of Small Pressurized Water
Reactors Under Four Feedback-Controlled Strategies
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Analysis of Integral Experiment of the AHWR Critical Facility with
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Mixcoatl Software (Part 2): Verification of 1D Fluid Flow Methods Coupled
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Radiolytic Production of Fluorine Gas from MSR Relevant Fluoride Salts
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Possible Does Not Mean Useful: The Role of Probability of Attack in
Security Risk Management
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Effects of Vent Size and Wind on Dispersion of Hydrogen Leaked in a
Partially Open Space: Studies by Numerical Analysis
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Bayesian Estimation of Cross-Section, Experimental Error, and Calculation
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Quantification of Deep Neural Network Prediction Uncertainties for VVUQ of
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New Security Concepts for Advanced Reactors
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A Dynamic Risk Framework for the Physical Security of Nuclear Power Plants
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Hybrid Variable Selection for Estimating Nominal HEPs and PIF Multipliers
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An Inline Burnup Algorithm
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Measurements of the 27Al(α,n) Thick Target Yield near Threshold
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Computing Physical Security System Effectiveness at Commercial Reactors
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Development, Verification, and Validation of an Advanced Systems Code
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(KP-FHR)
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Simulation of the High Temperature Test Facility (HTTF) Core Using the 2D
Ring Model with SAM
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A Perspective on Data-Driven Coarse Grid Modeling for System Level Thermal
Hydraulics
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Simulation of the Axial-Flow Centrifugal Bubble Separator for
Liquid-Fueled Molten Salt Reactors Using Eulerian Two-Fluid Model
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Numerical Investigations of Molten Salt Pump Journal Bearings Under
Hydrodynamic Lubrication Conditions for FHRs
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Beta-Ray-Bremsstrahlung Contributions to Short-Lived Delayed Photoneutron
Groups in Heavy Water Reactors
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Thermal-Hydraulic System-Level Analysis of a Molten Salt Natural
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Informing Performance Metrics of Advanced I&C Systems for Liquid Fueled
Fast Molten Salt Reactors
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  Authors: Yeongshin Jeong, Koroush Shirvan, Michael Buric
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Design and Thermal-Hydraulic Performance Analysis of a Low-Temperature
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  Authors: Ilyas Yilgor, Eymon Lan, Shanbin Shi
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  PubDate: 2022-08-01T02:32:00Z
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Validation and Uncertainty Quantification of Transient Reflood Models
Using COBRA-TF and Machine Learning Techniques Based on the NRC/PSU RBHT
Benchmark
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  Authors: Yue Jin, Stephen M. Bajorek, Fan-Bill Cheung
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  PubDate: 2022-07-28T03:56:06Z
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Reactor Physics Experiment on a Graphite-Moderated Core to Construct
Integral Experiment Database for HTGR
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  Authors: Shoichiro Okita, Yuji Fukaya, Atsushi Sakon, Tadafumi Sano, Yoshiyuki Takahashi, Hironobu Unesaki
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Pressure Drop in Seven-Pin Wire-Wrapped Rod Bundle for the Sodium
Cartridge Loop in Versatile Test Reactor
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  Authors: Zhengting Quan, Adam Dix, Ran Kong, Seungjin Kim, Mamoru Ishii, Mitchell T. Farmer
  Pages: 1 - 17
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-07-05T07:02:39Z
  DOI: 10.1080/00295639.2022.2082232
A Critical Review of Heat Pipe Experiments in Nuclear Energy Applications
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  Authors: Scott Wahlquist, Joshua Hansel, Piyush Sabharwall, Amir Ali
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-07-05T06:58:39Z
  DOI: 10.1080/00295639.2022.2082230
Flow-Induced Vibration of Solitary Wire-Wrapped Cylinders in Axial Flow
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  Authors: Chad A. Nixon, Wade R. Marcum
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-04-29T03:41:06Z
  DOI: 10.1080/00295639.2022.2058846