Stress Analysis for Reactor Coolant Pump Nozzle of Nuclear Reactor Pressure Vessel

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ISSN Print: 2327-4352
ISSN Online: 2327-4379
www.scirp.org/journal/jamp
E-mail: jamp@scirp.org

"Stress Analysis for Reactor Coolant Pump Nozzle of Nuclear Reactor Pressure Vessel"
written by Lijing Wen, Chao Guo, Tieping Li, Chunming Zhang,
published by Journal of Applied Mathematics and Physics, Vol.1 No.6, 2013

has been cited by the following article(s):

[1]	Experimental characterisation and numerical modelling of residual stresses in a nuclear safe-end dissimilar metal weld joint
	Metals, 2021

[2]	A Case Study on Stress Analysis of Nozzle Fitted On Pressure Vessel
	2016

[3]	Investigating Stress Level through FEA of Nozzles of Carbon Drain Vessel by ASME Sect-VIII
	International Research Journal of Engineering and Technology, 2015

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[1]	Experimental Characterisation and Numerical Modelling of Residual Stresses in a Nuclear Safe-End Dissimilar Metal Weld Joint Metals, 2021 DOI:10.3390/met11081298