Hydrodynamic buffer effect on the fall-off core barrel assembly in hypothetical drop accident-Reference-Cited by-同舟云学术

Hydrodynamic buffer effect on the fall-off core barrel assembly in hypothetical drop accident

Published:2018-06 Issue: Volume:332 Page:79-87
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Jiang Jin,Li Yanhui,Zhao Wensheng,Ying Rui,Fu You

Funder

National Natural Science Foundation of China

China Nuclear Power Engineering Co., Ltd

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

Reference22 articles.

1. Commissioning of the ATLAS thermal-hydraulic integral test facility;Kim;Ann. Nucl. Energy,2008

2. Thermal hydraulic analysis for grid supported pressurized water reactor cores;Shuffler;Nucl. Eng. Des.,2009

3. Study on mo steel for high temperature gas-cooled reactor material characterization of forged low Si mo steel;Okua;Nucl. Eng. Des.,1988

4. Selection of fuel cladding material for nuclear fission reactors;Azevedo;Eng. Fail. Anal.,2011

5. Study on a concrete filled structure for nuclear power plants;Takeuchi;Nucl. Eng. Des.,1998

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. Experimental study of turbulent coherent structures under different flow mixing devices in lower plenum of a scaled-down reactor pressure vessel;Nuclear Engineering and Design;2024-11

2. A universal formula for high-order added mass of reactor core barrel with lower core plate immersed in fluid;Progress in Nuclear Energy;2022-07

3. Mathematical model for predicting the vibration performance of a core barrel considering the interaction of seismic load and fluid force;Nuclear Engineering and Design;2021-11

4. Reliability analysis of girth welds by using finite element simulations with uncertain material properties;IOP Conference Series: Materials Science and Engineering;2021-01-01

5. Structural integrity assessment of secondary support structure and reactor pressure vessel following drop impact of core barrel assembly;Annals of Nuclear Energy;2019-12