Nuclear Technology aims to be the leading international publication reporting new information in the practical applications of nuclear science and technology. We publish technical papers, technical notes, critical reviews, rapid communications, book reviews, and letters to the editor on all phases of applications of fundamental research to nuclear technology.
《核技术》旨在成为报告核科学和技术实际应用新信息的领先国际出版物。我们出版技术论文、技术笔记、评论、快速通讯、书评和致编辑的信件，内容涉及基础研究在核技术应用的所有阶段。
Development of a Pragmatic Approach to Model Input Uncertainty Quantification for BEPU Applications
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1516055
Variable and Assured Peak Electricity Production from Base-Load Light-Water Reactors with Heat Storage and Auxiliary Combustible Fuels
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1518555
Technology, Policy, and Market Drivers of (and Barriers to) Advanced Nuclear Reactor Deployment in the United States After 2030
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1574119
TREAT Restart Project
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1589853
Fluoride-Salt-Cooled High-Temperature Test Reactor Thermal-Hydraulic Licensing and Uncertainty Propagation Analysis
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1610686
A Second Generation Multiphase-CFD Framework Toward Predictive Modeling of DNB
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1517528
Conceptual Design of a Pilot-Scale Pyroprocessing Facility
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1513243
Safety Strategy and Update of the TREAT Facility Safety Basis
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1556993
Transient Reactor Test Facility Advanced Transient Shapes
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1559712
FHR, HTGR, and MSR Pebble-Bed Reactors with Multiple Pebble Sizes for Fuel Management and Coolant Cleanup
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1573619
Response Matrix Method–Based Importance Solver and Variance Reduction Scheme in the Serpent 2 Monte Carlo Code
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1603710
Adsorption and Desorption of Tritium in Nuclear Graphite at 700°C: A Gas Chromatographic Study Using Hydrogen
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1590076
Transient Reactor Test (TREAT) Facility Initial Approach to Restart Criticality Following Extended Standby Operation
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1565471
Transient Reactor Test (TREAT) Facility Restart Heat Balance Calibration and Rod Worth Measurements
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1590075
Enhancing Electric Grid, Critical Infrastructure, and Societal Resilience with Resilient Nuclear Power Plants (rNPPs)
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1505357
Tritium Transport Analysis in a 2-MW Liquid-Fueled Molten Salt Experimental Reactor with the Code TMSR-TTAC
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1507200
Multiscaled Experimental Investigations of Corrosion and Precipitation Processes After Loss-of-Coolant Accidents in Pressurized Water Reactors
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1499324
Fluoride-Salt-Cooled High-Temperature Reactor (FHR) Using British Advanced Gas-Cooled Reactor (AGR) Refueling Technology and Decay Heat Removal Systems That Prevent Salt Freezing
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1586372
SHAKE-RoverD Framework for Nuclear Power Plants: A Streamlined Approach for Seismic Risk Assessment
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1494439
Rod Bundle Heat Transfer Thermal-Hydraulic Program
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1510697
Restarting the Transient Reactor Test (TREAT) Facility Reactor for Nuclear Transient Testing Science: A Special Issue of Nuclear Technology
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1650605
Design and Characterization of a Scintillator-Based Position-Sensitive Detector for Muon Imaging
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1522885
A New Two-Step Methodology for CANDU Analysis with the APEC-Assisted Nodal Equivalence Theory
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1582942
The CASUALIDAD Method for Uncertainty Evaluation of Best-Estimate System Thermal-Hydraulic Calculations
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1632092
Assessment of the Subchannel Code CTF for Single- and Two-Phase Flows
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1507221
Design and Optimization of a Fast Neutron Radiography System Based on a High-Intensity D-T Fusion Neutron Generator
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1575122
A Study of a Dose Constraint for Members of the Public Living Around Nuclear Power Plants in the United States
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1546536
Multigroup Cross-Section Generation with the OpenMC Monte Carlo Particle Transport Code
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1571828
Automated Identification of Causal Relationships in Nuclear Power Plant Event Reports
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1580967
Minor Actinide Transmutation in Supercritical-CO2-Cooled and Sodium-Cooled Fast Reactors with Low Burnup Reactivity Swings
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1601470
Electronic Stopping Powers of Formvar and Mylar Polymeric Materials for Heavy Ions: LSS Modified Theory and Monte Carlo Simulation
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1590071
Thermophysical Properties of Stainless Steel Containing 5 mass % B4C in the Solid Phase
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1607136
Quantile Regressions Applied to Pressurized Water Reactor CHF Correlation Safety Criteria
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1548220
Design, Fabrication, and Testing of Electrolytic Cell for Minimizing Simulated Active Waste
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1509586
Sensitivity Analysis of LB-LOCA in Response to Proposed 10 CFR 50.46c New Rulemaking
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1496694
Machine-Learning Analysis of Moisture Carryover in Boiling Water Reactors
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1583957
Foreword: Special issue on Restarting the Transient Reactor Test Facility
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1650604
Modeling of Aerosol Fission Product Scrubbing in Experiments and in Integral Severe Accident Scenarios
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1511213
Implementation of a Spacer Grid Rod Thermal-Hydraulic Reconstruction (ROTHCON) Capability into the Thermal-Hydraulic Subchannel Code CTF
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1585734
Uncertainty Analysis of the Conditional Exceedance Probability Calculation for a Probabilistically Significant SBO Sequence
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1494998
Methods of Data Collection in Nuclear Power Plants
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1610637
Commentary: Nuclear Energy for Economic Variable Electricity: Replacing the Role of Fossil Fuels
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1523623
Comparison of the Subchannel Code CTF to Steady-State and Transient Heat Transfer Experiments at Intermediate Pressures in Water
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1495000
Evaluation of Non-Oxide Fuel for Fission-Based Nuclear Reactors on Spacecraft
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1524228
A Data Model for Nuclear Power Plant Work Packages
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1601469
Development of Unstructured Mesh-Based Numerical Method for Sodium-Water Reaction Phenomenon
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1499323
The Effects of Plutonium Content and Self-Irradiation on Thermal Conductivity of Mixed Oxide Fuel
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1494999
A Mutual Information–Based Experimental Design Framework to Use High-Fidelity Nuclear Reactor Codes to Calibrate Low-Fidelity Codes
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1590073
Extraction of 137Cs from Acidic Feed by Centrifugal Contactors Using a Solution of Calix[4]arene-bis-1,2-benzo-crown-6 in Phenyltrifluoromethyl Sulphone
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2019.1575126
GPT-Free Sensitivity Analysis for Monte Carlo Models
来源期刊：Nuclear TechnologyDOI：10.1080/00295450.2018.1556062
