基于贝叶斯网络的核事故源项快速计算与预测技术研究

IF 1.5 4区工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Journal of Nuclear Science and Technology Pub Date : 2023-12-17 DOI:10.1080/00223131.2023.2294193

Mingliang Xie, Yuqing Chen, Lei Yu, Wei Wei, Boyu Chen, Zhengquan Xie, Xueyan Hou

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引用次数: 0

摘要

如何快速有效地评估和预测潜在的源条件对于应急响应非常重要。在本文中，传统的基于确定性的前瞻性分析计算方法已不再适用。

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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Technical research on rapid source term calculation and prediction technology of nuclear accidents based on Bayesian network

How to evaluate and predict potential source terms quickly and effectively is very important for emergency response. In this paper, the traditional forward analysis calculation based on determinist...

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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.