Damage development analysis of the whole nuclear power plant of AP1000 type under strong Main-aftershock sequences-Reference-Cited by-同舟云学术

Damage development analysis of the whole nuclear power plant of AP1000 type under strong Main-aftershock sequences

Published:2021-01 Issue: Volume:371 Page:110975
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Chen Wanruo,Zhang Yongshan,Wang Dayang^ORCID

Funder

National Natural Science Foundation of China

Natural Science Foundation of Guangdong Province

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference34 articles.

1. Tier 2, Chapter 3 “Design of structures, components, equipment and systems, revision 15;AP1000 Design Control Document,2004

2. Seismic design criteria for structures, systems and components in nuclear facilities;ASCE 43–05,2005

3. Seismic analysis of safety-related nuclear structures and commentary;ASCE 4–98,2000

4. New advances in the seismic analysis of nuclear structures and equipment from the SINAPS@ project;Banci,2018

5. Fragility analysis of a containment structure under far-fault and near-fault seismic sequences considering post-mainshock damage states;Bao;Eng. Struct.,2019

Cited by 7 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. An improved lump mass stick model of a nuclear power plant based on the Kriging surrogate model;Nuclear Engineering and Design;2024-07

2. Seismic fragility assessment of aqueduct bent structures subjected to mainshock-aftershock sequences;Engineering Structures;2023-10

3. Stochastic dynamic and reliability analysis of AP1000 nuclear power plants via DPIM subjected to mainshock-aftershock sequences;Reliability Engineering & System Safety;2023-07

4. Seismic performance evaluation of reactor containment building considering effects of concrete material models and prestressing forces;Nuclear Engineering and Technology;2023-05

5. Seismic fragility analysis of the inter-story isolated structure for the influence of main-aftershock sequences;Advances in Mechanical Engineering;2023-01