Development of nuclear fuel assembly 3D reduced model and modal analysis

Author:

Subhan Muhammad,Namgung Ihn

Funder

Korea Electric Power Corporation

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference13 articles.

1. US NRC document APR1400-Z-M-NR-14040-NP, ML15008A447, Structural Analysis of Fuel Assemblies for Seismic and Loss of Coolant Accident Loading, Rev.0, KHNP,(2014) 28-34. https://www.nrc.gov/docs/ML1500/ML15008A447.pdf.

2. ANSYS mechanical Properties, Data Compiled by The Granta Design Team at ANSYS, incorporating various sources including JAHM and MagWeb, ANSYS R1 Version, ANSYS, Inc. All Rights Reserved. Printed in U.S.A. (2020).

3. Seismic analysis of the APR 1400 reactor vessel internals using the model reduction method;Choi. Youngin,;Journal of Nuclear Science and Technology,2016

4. Development of core seismic analysis models for KNGR fuel assemblies associated with 0.3 g seismic loads;Kim;Nuclear Engineering and Design,2002

5. Kim, Han-Gon, The Design Characteristics of Advanced Power Reactor 1400, IAEA-CN-164-3S09.

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