American Nuclear Society
Join ANS|Member Center|ANS Store|Contact Us
Home

Home / Publications / Journals / Nuclear Technology / Volume 211

Volume 211

Number 1 | Number 1S | Number 2 | Number 3 | Number 4 | Number 5

Number 1

Reconstruction of γ Dose Rate Field and Algorithm Validation Based on Inverse Distance Weight Interpolation

Biao Zhang, Jinjia Cao, Shuang Lin, Yingming Song

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 1-12

Research Article / dx.doi.org/10.1080/00295450.2024.2312026

Startup and Multiphysics Analysis of a Compact kW-Class Thermal Spectrum Microreactor

Vedant K. Mehta, Aditya P. Shivprasad, Dasari V. Rao

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 13-31

Research Article / dx.doi.org/10.1080/00295450.2024.2312483

Experimental Study on Combustion Characteristics of Solvent and Fire Behavior During a Solvent Fire at Nuclear Fuel Cycling Facility

Hongchao Sun, Yiren Lian, Guoqiang Li, Lei Chen, Dongyuan Meng, Shutang Sun, Dajie Zhuang, Jiangang Zhang

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 32-38

Research Article / dx.doi.org/10.1080/00295450.2024.2312723

Extrapolation of Monte Carlo–Derived Noble Gas Air-Submersion Effective Dose Rate Coefficients for Selected Occupational Settings to Other Geometries and Radionuclides

John N. Hamawi, Pedro B. Pérez

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 39-53

Research Article / dx.doi.org/10.1080/00295450.2024.2315362

Sparse-View Neutron Computed Tomography 3-D Reconstruction via the Fast Gradient Projection Algorithm

Tengfei Zhu, Yang Liu, Xiaoping Ouyang

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 54-65

Research Article / dx.doi.org/10.1080/00295450.2024.2318049

Delayed Heating Calculations Using the MCNP-ORIGEN Activation Automation Tool

Roberto E. Fairhurst-Agosta, Tomasz Kozlowski

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 66-78

Research Article / dx.doi.org/10.1080/00295450.2024.2319922

Progress in Fast Modular Reactor Conceptual Design

Hangbok Choi, John Bolin, Oscar Gutierrez, Radu Curiac, Mohammad Alavi, Matthew Virgen, Ed Chin, James Beaver, Pascal Brocheny, Geoffrey Beausoleil, Abdellatif M. Yacout, Sal Rodriguez, Michael Corradini, Daejong Kim, Steven L. Krahn, Eric Thornsbury

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 79-92

Research Article / dx.doi.org/10.1080/00295450.2024.2319925

Development of a New Correlation for Saturated Flow Boiling Heat Transfer in a Helically Coiled Tube

Min Gi Kim, Byongjo Yun, Jae Jun Jeong

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 93-110

Research Article / dx.doi.org/10.1080/00295450.2024.2319926

Modified Evaporation Model for ATHLET System Code in a Passive Containment Cooling System for Nuclear Safety

Michel Haag, Iurii Dolganov, Stephan Leyer

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 111-126

Research Article / dx.doi.org/10.1080/00295450.2024.2319933

PCMI Uncertainty and Sensitivity Analysis of Es-Salam Reactor Fuel Rods During Steady-State Operations

Djillali Saad, Mohamed Elhadi Boulheouchat, Mohamed Bouaouina, Tahar Zidi

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 127-142

Research Article / dx.doi.org/10.1080/00295450.2024.2323226

Evaluation of Reaction Rate Distribution for Shielding Region in the Prototype Fast Reactor Monju

Tetsuya Mouri, Taira Hazama, Hiroki Katagiri, Kazuya Ohgama

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 143-160

Research Article / dx.doi.org/10.1080/00295450.2024.2323228

Verification and Validation of Spectral Element Code for Supercritical CO2 Flow in Vertical Heated Tubes

Haomin Yuan, Tri Nguyen, Elia Merzari, Dillon Shaver, Ananias Tomboulides

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 161-183

Research Article / dx.doi.org/10.1080/00295450.2024.2323229

Number 1S

Key Technologies for Korean Space Heat Pipe Reactor

Byung Ha Park, Chan Soo Kim, Sung Hoon Choi, Sung Nam Lee

Nuclear Technology / Volume 211 / Number 1S / April 2025 / Pages S1-S11

Research Article / dx.doi.org/10.1080/00295450.2023.2289750

Exploring the Feasibility of Kuiper Belt Missions Supported by Centrifugal Nuclear Thermal Propulsion

William Ziehm, L. Dale Thomas

Nuclear Technology / Volume 211 / Number 1S / April 2025 / Pages S12-S20

Research Article / dx.doi.org/10.1080/00295450.2024.2323242

Developing a Three-Dimensional Bubble Dynamics Model for Centrifugal Nuclear Thermal Propulsion

Pongkrit Darakorn na Ayuthya, Jason T. Cassibry

Nuclear Technology / Volume 211 / Number 1S / April 2025 / Pages S21-S37

Research Article / dx.doi.org/10.1080/00295450.2024.2348746

Feasibility of a Small, Low-Power RTG Concept Utilizing a GPHS Heat Source

Kenton Sherick, Aniruddha Ray, Pierre Berneron, B. Allen Tolson, Chadwick Barklay, Maarten den Heijer, Christofer E. Whiting

Nuclear Technology / Volume 211 / Number 1S / April 2025 / Pages S38-S48

Research Article / dx.doi.org/10.1080/00295450.2024.2369825

Fission Surface Power—A Conceptual 350-kW(thermal) Microreactor Designed for Lunar Power Around SpaceX Falcon Heavy Mass Constraints

Daniel L. P. Watson, Ronald Daryll E. Gatchalian, Hui-Yu Hsieh, Pramatha Bhat, Pavel V. Tsvetkov

Nuclear Technology / Volume 211 / Number 1S / April 2025 / Pages S49-S61

Research Article / dx.doi.org/10.1080/00295450.2024.2423144

Number 2

Fluid-Solid Interaction Analysis at the Slip Joint of a Boiling Water Reactor Type 5 Jet Pump

J. Cruz-Castro, L. H. Hernández-Gómez, Y. López-Grijalba, E. Hernández-Palafox, J. A. Beltrán-Fernández, J. I. E. Palacios-Hernández, I. A. Alarcón-Sánchez

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 185-199

Research Article / dx.doi.org/10.1080/00295450.2024.2323239

A Study on Boiling Heat Transfer Performance of TiO2-CNTs Hybrid Nanofluid on a Downward-Facing Heating Surface

Songling Liu, Huai-En Hsieh, Shiqi Wang

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 200-213

Research Article / dx.doi.org/10.1080/00295450.2024.2323240

Theoretical Calculation of Gamma-Ray and Neutron Shielding Properties for CsPbBr3-Polypropylene Composite Material

Junfeng Zhao, Yuanjie Sun, Yue Zhang, Zhigang Li, Hongtao Zhao, Qingyu Wang

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 214-224

Research Article / dx.doi.org/10.1080/00295450.2024.2323257

Neutronic Analysis of the Conceptual Molten Uranium Breeder Reactor Using MCNP and SCALE Tools

Zeyun Wu, Christian Pochron, Mihai (Mike) G. M. Pop, Neal Mann

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 225-240

Research Article / dx.doi.org/10.1080/00295450.2024.2323267

Turbulent Particle Flow in Spent Nuclear Fuel Storage Systems

Sarah R. Suffield, William A. Perkins, Ben J. Jensen, Brady D. Hanson, Steven B. Ross

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 241-257

Research Article / dx.doi.org/10.1080/00295450.2024.2324213

Development and Verification of Neutron Kinetics Parameter Calculation Program Applicable to Subcritical Systems of Long-Life Reactors

Shikun Xu, Lingyi Qu, Tao Yu, Jinsen Xie, Ji Tong, Zining Ni, Nianbiao Deng, Hiroshi Watabe

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 258-272

Research Article / dx.doi.org/10.1080/00295450.2024.2324513

Mixing of Hydrogen-Steam Buoyancy Jets Released into the Upper Atmosphere of the Containment Building

Youngsu Na

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 273-285

Research Article / dx.doi.org/10.1080/00295450.2024.2325738

Effect of Cooling Pump Transient Power Supply on ETRR-2 Safety Parameters

Abdelfatah Abdelmaksoud, Asmaa Gamal, Ahmed R. Adly

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 286-297

Research Article / dx.doi.org/10.1080/00295450.2024.2325739

Development of Obligation Tracking System for Internationally Controlled Items in Accordance with Bilateral Nuclear Cooperation Agreements

Mun-Young Ryu, Hyun-Jo Kim, Jin-Ha Choi

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 298-317

Research Article / dx.doi.org/10.1080/00295450.2024.2325742

Novel Approach for Network Data Exchange Among Safety-Related Control Systems of Nuclear Reactors

Aditya Gour, R. P. Behera, Tom Mathews

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 318-331

Research Article / dx.doi.org/10.1080/00295450.2024.2325749

Surrogate Model of Solved Poisson Kriging Method for Radiation Field Reconstruction

Zhenyu Wang, Zungang Wang, Jian Sun, Zhiyuan Li, Shanxue Xi, Xing Wei, Weiqi Huang, Chunzhi Zhou

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 332-343

Research Article / dx.doi.org/10.1080/00295450.2024.2325751

Evaluating Material Attractiveness of Minor Actinide Nuclear Fuel Intended for a Waste Transmutation Lead-Cooled Fast Reactor

Débora M. Trombetta, Erik Branger, Markus Preston, Sophie Grape

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 344-357

Research Article / dx.doi.org/10.1080/00295450.2024.2326374

Risk Plus Some Attributes (R + SA): A New Risk-Informed Method for Prioritizing Inspection Activities During New Fuel Facility Construction

Peter Yarsky, Kevin Coyne, Cynthia Taylor, Chad Oelstrom

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 358-376

Research Article / dx.doi.org/10.1080/00295450.2024.2326375

Number 3

Two-Fluid and Discrete Population Balance Model for Simulation of Batch Sedimentation Relevant to Plutonium Reconversion

Saroj Kumar Panda, Panantharayil Vishnu Anand, Vivek Kumar Mishra, Ramachandran Pillai Rajeev, Konda Athmaram Venkatesan, Krishnamurthy Ananthasivan

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 377-399

Research Article / dx.doi.org/10.1080/00295450.2024.2326714

Lightweight Heat Pipe Radiator for Nuclear Reactor Power Systems on Lunar Surface

Mohamed S. El-Genk, Timothy M. Schriener

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 400-428

Research Article / dx.doi.org/10.1080/00295450.2024.2329830

Combustion Properties of Glove-Box Panel Resins Under Fire Accidents

Shinsuke Tashiro, Gunzo Uchiyama, Takuya Ohno, Yuki Amano, Ryoichiro Yoshida, Koji Watanabe, Hitoshi Abe, Yuichi Yamane

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 429-438

Research Article / dx.doi.org/10.1080/00295450.2024.2329832

Calculation and Discussion for Crack Driving Force of Dissimilar Metal Welded Joint of Nuclear Power Equipment Nozzle and Safe End

Dasheng Wang, Jin Ting, Xu Xiao, Tan Jianping, Zhang Kun, Wang Guozhen

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 439-451

Research Article / dx.doi.org/10.1080/00295450.2024.2329833

Flow Regime Classification in Hexagonal Wire-Wrapped Fuel Assembly Using Advanced Machine Learning Models

Hansol Kim, Joseph Seo, Yassin Hassan

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 452-475

Research Article / dx.doi.org/10.1080/00295450.2024.2331897

Analytical Model of Natural Circulation with a Sinusoidal Heat Input in a PWR

M. W. Abdulrahman

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 476-499

Research Article / dx.doi.org/10.1080/00295450.2024.2337234

Feasibility Analysis of Tritium Measurement in the Aqueous Medium Based on a Plastic Scintillating Fiber Array

Wenyu Cheng, Linlin Zeng, He Zhou, Jie Liang, Ke Deng, Qin Zhang, Wei Liu

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 500-512

Research Article / dx.doi.org/10.1080/00295450.2024.2338508

Evaluation of Fukushima Daiichi Unit 1 Ex-Vessel Phenomenon Leveraging on Primary Containment Vessel Robotic Inspections

Michal Cibula, Marco Pellegrini, Masato Mizokami, Shinya Mizokami

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 513-530

Research Article / dx.doi.org/10.1080/00295450.2024.2339578

Analysis of AP1000 Small-Break Loss-of-Coolant Accident Using Reactor Transient Simulator

Hossam H. Abdellatif, Palash K. Bhowmik, David Arcilesi, Piyush Sabharwall

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 531-547

Research Article / dx.doi.org/10.1080/00295450.2024.2342168

Methodology for Multiparameter Evaluation of Barriers Against Proliferation of Minor Actinides

Markus Preston, Erik Branger, Vitaly Fedchenko, Sophie Grape, Robert E. Kelley, Vaibhav Mishra, Débora M. Trombetta

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 548-569

Research Article / dx.doi.org/10.1080/00295450.2024.2342184

Development of a Potential Facility Risk Index for Nuclear Safety and Security Using a Terrorism Scenario with a Hypothetical Nuclear Facility

Joeun L. Kot, Theodore Thomas, Jason T. Harris

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 570-583

Research Article / dx.doi.org/10.1080/00295450.2024.2343971

Failure Analysis of CRDINiCr Butterfly Valves for Nuclear Power Plant Applications

Jian Cheng, Kewei Fang, Kexun Fei, Qiang Wang, Bo Li, Eduardo B. Farfán

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 584-597

Research Article / dx.doi.org/10.1080/00295450.2024.2344912

Determination of Airborne Release Fractions from Loose Powder Contamination Under Impact Stress

Mellissa Komninakis, Joseph Sinicrope, James C. Nicholson, Philip Moore, Yolanda Rodriguez, Leonel Lagos, Daniela Radu

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 598-606

Research Article / dx.doi.org/10.1080/00295450.2024.2345945

Prolonged Operation of Hydro-Accumulators in VVER-1000/V446 Considering Flow Restriction Components

Seyed Ali Hosseini, Alireza Najafi, Amir Saeed Shirani, César Queral, Francesco D’Auria

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 607-623

Note / dx.doi.org/10.1080/00295450.2024.2337313

Surface-Activated Graphite Oxide Nanosheets with Promoted U(VI) Adsorption Performance

Jianwei Zhang, Tuo Li, Bo Tian, Jinfeng Li, Wenze Li, Abdullah, Nan Zhang, Hongtao Zhao

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 624-634

Note / dx.doi.org/10.1080/00295450.2024.2343116

Number 4

A Review on the Development of Single-Moderator-Based Neutron Spectrometers

Rasito Tursinah, Sidik Permana, Zaki Su’ud, Alan Maulana, Putu Sukmabuana

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 635-644

Review Article / dx.doi.org/10.1080/00295450.2024.2361177

Nonhomogeneous Poisson Process Model for Estimating Mean Time Between Failures of the JE01-AP03 Primary Pump Implemented on the RSG-GAS Reactor

Sri Sudadiyo

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 645-660

Review Article / dx.doi.org/10.1080/00295450.2024.2352663

Safety Assessment Methodology for Transportation of Radioactive Material via Train

Manorma Kumar, Guillem Cortes Rossell

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 661-673

Review Article / dx.doi.org/10.1080/00295450.2024.2356328

Validation of McCARD Monte Carlo Calculation Code Against NAA Experiments Using Rare Earth Element Certified Reference Material Activated at JRTR

Rashdan Malkawi, Sayel Marashdeh, Kafa Al-Khasawneh, Aseel Al-Mohammad, Mahmoud Suaifan, Mohammad Omari, Majd Hawwari

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 674-689

Research Article / dx.doi.org/10.1080/00295450.2024.2346869

The Use of High-Density UN Fuel in Heat-Pipe Microreactors

Cihang Lu, Erofili Kardoulaki, Nicolas E. Stauff, Arantxa Cuadra

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 690-707

Research Article / dx.doi.org/10.1080/00295450.2024.2348732

Electrochemical Identification of Metal Chlorides in Eutectic LiCl-KCl Without Prior Knowledge of Analyte Identities

Tyler Williams, Jason Torrie, Mark Schvaneveldt, Ranon Fuller, Greg Chipman, Devin Rappleye

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 708-724

Research Article / dx.doi.org/10.1080/00295450.2024.2348849

Fluid Dynamics Effects of a Porous Blockage on Laminar Flow in the Interior Subchannels of a 61-Pin Wire-Wrapped Rod Bundle

Trevor Melsheimer, Craig Menezes, Yassin A. Hassan

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 725-741

Research Article / dx.doi.org/10.1080/00295450.2024.2348853

Examining Low-Energy Gamma-Ray Protection of a New Cement Product as an Alternative Cementitious Material Using Geant4 Software

Muneerah A. Al-Aqeel

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 742-754

Research Article / dx.doi.org/10.1080/00295450.2024.2355405

Investigation of the Thermal Effects of MgO and ZnO Nanoparticles in a Pressurized Water Reactor Coolant with Computational Fluid Dynamics Model

Sinem Uzun

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 755-767

Research Article / dx.doi.org/10.1080/00295450.2024.2356331

Refueling Considerations for 99Mo Production in a CANDU Reactor

J. Haroon, E. Nichita

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 768-776

Research Article / dx.doi.org/10.1080/00295450.2024.2357917

CHF Enhancement by γ-Fe2O3 Nanofluids with Pool Boiling Condition on a Downward-Facing Plane

Xintian Cai, Huai-En Hsieh, Zhibo Zhang, Shiqi Wang, Saikun Wang

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 777-789

Research Article / dx.doi.org/10.1080/00295450.2024.2361180

Numerical Study of Porous Cylindrical Containment for the Fuel Element of a Centrifugal Nuclear Thermal Rocket

Pramatha Bhat, Kendall R. Adams, Stephen J. Herring, Brad Kirkwood

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 790-806

Research Article / dx.doi.org/10.1080/00295450.2024.2361185

Investigation of Lunar Shallow Subsurface Water Content and Soil Elemental Composition via Active Neutron Detection

Huanyu Han, Xiaoyu Li, Zhi Chen

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 807-820

Research Article / dx.doi.org/10.1080/00295450.2024.2361194

Discrete Element Method Simulation of Vibratory Filling of Convoluted Hot Isostatic Pressing Canisters Using Idaho Calcine Waste Simulant

Simon Chung, Martin Stewart, Peter Wypych, David Hastie, Andrew Grima, Sam Moricca

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 821-847

Research Article / dx.doi.org/10.1080/00295450.2024.2361195

Discrete Element Method Simulation of the Idaho Calcine Simulant for Hot Isostatic Pressing Canister Filling Process: Part 2

Simon Chung, Martin Stewart, Peter Wypych, David Hastie, Andrew Grima, Sam Moricca

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 848-861

Research Article / dx.doi.org/10.1080/00295450.2024.2361190

Number 5

Response to the Seawater Contamination Event at Hamaoka Unit 5 and the Effects of Corrosion by Seawater

Koichiro Omura

Nuclear Technology / Volume 211 / Number 5 / May 2025 / Pages 863-888

Review Article / dx.doi.org/10.1080/00295450.2024.2368960

Processes and Interactions of Potential Relevance for Deep Geological Disposal of HLW and L/ILW at the Same Site—International Approaches and Transferability to the German Site Selection

Marie Voss, Ute Maurer-Rurack, Andreas Poller

Nuclear Technology / Volume 211 / Number 5 / May 2025 / Pages 889-904

Review Article / dx.doi.org/10.1080/00295450.2024.2368976

Recent Developments and Findings of Heat Pipe Experiments for Microreactor Applications

Ilyas Yilgor, Zachary D. Sellers, Jeremy L. Hartvigsen, Katrina M. Sweetland, Pei-Hsun Huang, Taehwan Ahn, Joseph Seo, Annalisa Manera, Victor Petrov, Mark Anderson, Yassin Hassan, Shanbin Shi, Piyush Sabharwall

Nuclear Technology / Volume 211 / Number 5 / May 2025 / Pages 905-939

Review Article / dx.doi.org/10.1080/00295450.2024.2375488

An Optimal Radiation Shield Design of a Small Modular Nuclear Power Reactor by Genetic Algorithm

S. Bagheri, H. Khalafi, A. A. Bahrami

Nuclear Technology / Volume 211 / Number 5 / May 2025 / Pages 940-952

Research Article / dx.doi.org/10.1080/00295450.2024.2362524

Performance Analysis of U3Si2-Al Fuel with Density of 2.96 gU/cm3 and Burnup of 56%

Maman Kartaman Ajiriyanto, Aslina Br. Ginting, Sungkono, Supardjo, Juan Carlos Sihotang

Nuclear Technology / Volume 211 / Number 5 / May 2025 / Pages 953-962

Research Article / dx.doi.org/10.1080/00295450.2024.2365485

Neutronics–Thermal-Hydraulics–Coupled Transient Analysis for Reactor Power Change in an Inclined Offshore Floating Boiling Water Reactor

Kodai Fukuda, Toru Obara, Kenya Suyama

Nuclear Technology / Volume 211 / Number 5 / May 2025 / Pages 963-973

Research Article / dx.doi.org/10.1080/00295450.2024.2368966

Research on Active Disturbance Rejection Control of Small Modular Reactor Once-Through Steam Generator Based on Differential Evolution Optimization Algorithm

Wei Guo, Bo Shi, Tao Zhang, Zhijiang Wu, Guohua Xiong, Minjun Peng

Nuclear Technology / Volume 211 / Number 5 / May 2025 / Pages 974-993

Research Article / dx.doi.org/10.1080/00295450.2024.2368973

Exploring the Feasibility of Quantum-Based Secure Communications for Nuclear Applications

Konstantinos Gkouliaras, Vasileios Theos, Stylianos Chatzidakis

Nuclear Technology / Volume 211 / Number 5 / May 2025 / Pages 994-1013

Research Article / dx.doi.org/10.1080/00295450.2024.2368977

Calculation of Isotope-Specific Fission Rates for Neutrino Source Calculation in PWR Fuel Diversion Safeguarding

Dean Price, Leia Barrowes, James Wells, Brendan Kochunas

Nuclear Technology / Volume 211 / Number 5 / May 2025 / Pages 1014-1043

Research Article / dx.doi.org/10.1080/00295450.2024.2369476

Fiberoptic Laser-Induced Breakdown Spectroscopy System for in situ Measurement in a Hazardous Environment

Yichen Zhao, Haori Yang, Sivanandan S. Harilal

Nuclear Technology / Volume 211 / Number 5 / May 2025 / Pages 1044-1055

Research Article / dx.doi.org/10.1080/00295450.2024.2370193

Design and Development of a Portable Neutron Detection System Based on a 6Li-Doped ZnS(Ag) Scintillator

Tuğçe Gürdal, Haluk Yücel

Nuclear Technology / Volume 211 / Number 5 / May 2025 / Pages 1056-1065

Research Article / dx.doi.org/10.1080/00295450.2024.2370701

Hazard Identification Risk Assessment Onsite Survey for External Human-Induced Events Aspect of the Nuclear Power Plant in West Kalimantan, Indonesia

Khusnul Khotimah, Widjanarko, Siti Alimah, Budi Santoso, Sriyana, Kurnia Anzhar, Joko Waluyo, Gustini H. Sayid, Rismiyanto, Hadi Suntoko, Fepriadi, Nicholas Bertony Saputra, Agus Teguh Pranoto, Yulaida Maya Sari, Ika Wahyu Setya Andani

Nuclear Technology / Volume 211 / Number 5 / May 2025 / Pages 1066-1079

Research Article / dx.doi.org/10.1080/00295450.2024.2374660

A RELAP5-3D Model of the Lobo Lead Loop

Jonathan L. Barthle, Nicholas Meehan, G. Ivan Maldonado, Nicholas R. Brown

Nuclear Technology / Volume 211 / Number 5 / May 2025 / Pages 1080-1091

Research Article / dx.doi.org/10.1080/00295450.2024.2374661

Nuclear Reactor Operations Education and Training with Virtual Reality and an Immersive Desktop Application

Shikha Prasad, Oscar L. Delgado, Alexander Tucker, Sunay Palsole

Nuclear Technology / Volume 211 / Number 5 / May 2025 / Pages 1092-1102

Note / dx.doi.org/10.1080/00295450.2024.2368980

Comparative Study of Raman and EPMA Elemental Mapping of an Unirradiated MOX Sample

Jean-Yves Colle, Philipp Pöml, Jacobus Boshoven, Rudy J. M. Konings

Nuclear Technology / Volume 211 / Number 5 / May 2025 / Pages 1103-1110

Note / dx.doi.org/10.1080/00295450.2024.2377012

 

Home|Contact Us|Invoice Payment|Nuclear Links

Privacy Policy|Terms of Use