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230 MeV/u α粒子撞击铝时带电粒子发射的双差分截面

IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY
Journal of Nuclear Science and Technology Pub Date : 2023-12-27 DOI:10.1080/00223131.2023.2294192
Toshimasa Furuta, Yusuke Uozumi, Yuji Yamaguchi, Yosuke Iwamoto, Yusuke Koba, Elena Velicheva, Vladimir Kalinnikov, Zviadi Tsamalaidze, Petr Evtoukhovitch
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引用次数: 0

摘要

通过测量轰击铝靶的 230-MeV/u α 粒子，对 α 粒子碎裂反应产生的带电粒子进行了实验研究。双差分交叉...
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Double-differential cross sections for charged particle emissions from α particle impinging on Al at 230 MeV/u
Charged particle production from α particle fragmentation reactions was investigated experimentally by measurement of 230-MeV/u α particles bombarding an aluminum target. Double differential cross ...
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来源期刊
Journal of Nuclear Science and Technology
Journal of Nuclear Science and Technology 工程技术-核科学技术
CiteScore
2.40
自引率
16.70%
发文量
116
审稿时长
2.3 months
期刊介绍： 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, Safeguard Radiation, 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 Technology Nuclear 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 Processing Thermal Hydraulics: Thermal Hydraulic Experiment and Analysis, Thermal Hydraulic Design, Thermal Hydraulics of Single/Two/Multi Phase Flow, Interactive Phenomena with Fluid, Measurement Technology...etc.
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