Analysis and optimization research on latch life of control rod drive mechanism based on approximate model-Reference-Cited by-同舟云学术

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Analysis and optimization research on latch life of control rod drive mechanism based on approximate model

Published:2021-12 Issue:12 Volume:53 Page:4166-4178
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Ling Sitong^ORCID,Li Wenqiang,Yu Tianda,Deng Qiang,Fu Guozhong

Funder

Sichuan Province Science and Technology Support Program

National Natural Science Foundation of China

Science and Technology Department of Sichuan Province

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference37 articles.

1. Fragility assessment for electric cabinet in nuclear power plant using response surface methodology;Tran;Nuclear Engineering and Technology,2019

2. Research on the structure design of the LBE reactor coolant pump in the lead base heap;Lu Yonggang;Nuclear Engineering and Technology,2019

3. Kim Min-Kyu Seismic fragility evaluation of the base-isolated nuclear power plant piping system using the failure criterion based on stress-strain;Kim Sung-Wan;Nuclear Engineering and Technology,2019

4. Evaluation of gamma-ray and neutron attenuation properties of some polymers;Kaçal;Nuclear Engineering and Technology,2019

5. Determination of indoor doses and excess lifetime cancer risks caused by building materials containing natural radionuclides in Malaysia;Abdullahi;Nuclear Engineering and Technology,2019

Cited by 11 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Development and Application of Control Rod Drive Mechanism Latch Assembly Inspection Equipment;2024 IEEE 2nd International Conference on Power Science and Technology (ICPST);2024-05-09

2. A new monitoring method for control rods position of small modular reactors (SMRs)-based coaxial capacitor;Nuclear Engineering and Design;2024-02

3. Multi-objective optimization application for a coupled light water small modular reactor-combined heat and power cycle (cogeneration) systems;Nuclear Engineering and Technology;2023-12

4. Binocular Vision System for Measuring the Height of Control Rod Drive Rod in Nuclear Reactor;2023 42nd Chinese Control Conference (CCC);2023-07-24

5. Static performance of capacitance control rod position sensor: A review;Progress in Nuclear Energy;2023-07

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