利用过氧化钠融合技术开发分析燃料碎片元素组成的溶解方法

IF 1.5 4区工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Science and Technology Pub Date : 2024-07-17 DOI:10.1080/00223131.2024.2381553

Satoshi Nakamura, Sho Ishii, Hitoshi Kato, Yasutoshi Ban, Kenta Hiruta, Takuya Yoshida, Hiroyuki Uehara, Hiroki Obata, Yasuhiko Kimura, Masahide Takano

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引用次数: 0

摘要

利用过氧化钠（Na2O2）融合技术开发了一种分析燃料碎片元素组成的溶解方法。在这种方法中，两种不同类型的模拟燃料残片都会被溶解到过氧化...

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Development of a dissolution method for analyzing the elemental composition of fuel debris using sodium peroxide fusion technique

A dissolution method for analyzing the elemental composition of fuel debris using the sodium peroxide (Na2O2) fusion technique has been developed. Herein, two different types of simulated fuel debr...

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来源期刊

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.