影响镍基合金 82 焊接金属电化学腐蚀电位的高温电化学反应参数

IF 1.5 4区工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Science and Technology Pub Date : 2024-02-09 DOI:10.1080/00223131.2024.2317225

Yoichi Wada, Hikari Murotani, Kazushige Ishida, Mayu Sasaki, Makoto Nagase, Ryosuke Shimizu, Shinobu Okido

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引用次数: 0

摘要

测量了镍基合金 82 焊接金属（合金 82）在氧气和 H2O2 环境中的电化学腐蚀电位 (ECP) 数据。虽然镍基合金 82 被用于锅炉、电动机和变压器的各种焊缝中，但其在氧气和 H2O2 环境中的电化学腐蚀电位（ECP）数据并不准确。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of nickel-base alloy 82 weld metal

The electrochemical corrosion potential (ECP) data of nickel-base alloy 82 weld metal (Alloy 82) in both O2 and H2O2 environments were measured. Although Alloy 82 is used at various welds in boilin...

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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.