Journal of Nuclear Science and Technology

期刊简介：The Journal of Nuclear Science and Technology (JNST) publishes internationally peer-reviewed papers that contribute to the exchange of research, ideas and developments in the field of nuclear science and technology, to contribute peaceful and sustainable development of the World.JNST ’s broad scope covers a wide range of topics within its subject category, including but are not limited to:General Issues related to Nuclear Power Utilization: Philosophy and Ethics, Justice and Policy, International Relation, Economical and Sociological Aspects, Environmental Aspects, Education, Documentation and Database, Nuclear Non-Proliferation, SafeguardRadiation, Accelerator and Beam Technologies: Nuclear Physics, Nuclear Reaction for Engineering, Nuclear Data Measurement and Evaluation, Integral Verification/Validation and Benchmark on Nuclear Data, Radiation Behaviors and Shielding, Radiation Physics, Radiation Detection and Measurement, Accelerator and Beam Technology, Synchrotron Radiation, Medical Reactor and Accelerator, Neutron Source, Neutron TechnologyNuclear Reactor Physics: Reactor Physics Experiments, Reactor Neutronics Design and Evaluation, Reactor Analysis, Neutron Transport Calculation, Reactor Dynamics Experiment, Nuclear Criticality Safety, Fuel Burnup and Nuclear Transmutation,Reactor Instrumentation and Control, Human-Machine System: Reactor Instrumentation and Control System, Human Factor, Control Room and Operator Interface Design, Remote Control, Robotics, Image ProcessingThermal Hydraulics: Thermal Hydraulic Experiment and Analysis, Thermal Hydraulic Design, Thermal Hydraulics of Single/Two/Multi Phase Flow, Interactive Phenomena with Fluid, Measurement Technology...etc.

【译文】《核科学与技术杂志》（JNST）发表国际同行评审的论文，旨在促进核科学与技术领域的科研、思想和发展的交流，以促进世界的和平与可持续发展。JNST 的广泛范围涵盖了其主题类别内的广泛主题，包括但不限于：与核能利用相关的一般问题：哲学与伦理、正义与政策、国际关系、经济和社会方面、环境方面、教育、文档和数据库、核不扩散、保障、辐射、加速器和束技术、核物理、工程用核反应、核数据测量与评估、核数据综合验证/验证和基准、辐射行为和屏蔽、辐射物理学、辐射检测与测量、加速器和束技术、同步辐射、医疗反应堆和加速器、中子源、中子技术、核反应堆物理学：反应堆物理实验、反应堆中子学设计评估、反应堆分析、中子输运计算、反应堆动力学实验、核临界安全、燃料燃耗和核嬗变、反应堆仪表和控制、人机系统：反应堆仪表和控制系统、人因工程、控制室和操作员界面设计、遥控、机器人、图像处理、热工水力：热工水力实验和分析、热工水力设计、单相/两相/多相流的热工水力、与流体的相互作用现象、测量技术等。