Published August 2013 | Version v1
Journal article

Methodology for seismic analysis of FBR core assembly using variable added damping

  • 1. China Nuclear Power Technology Research Institute, Shenzhen (China)
  • 2. North China Electric Power University, Beijing (China)
  • 3. China Nuclear Power Design Co., Ltd., Shenzhen (China)

Description

It is necessary to consider the fluid-solid coupling effect due to the interaction between coolant and core assembly when analyzing the seismic performance of the FBR core assembly. The added damping was treated mostly as a constant in previous researches. In fact, the effect on assemblies from the coolant depends strongly on the gap between the core assemblies, and the damping should be considered as a variable. In order to simulate the vibration of the core assembly more accurately, the methodology for the seismic analysis of FBR core assemblies using variable added damping was studied. In this paper, the seismic analysis model of one single row of core assemblies (5 assemblies) of FBR was established. By comparing the two kinds of added damping models, the constant and variable ones respectively, the results show that the seismic analysis of the core assemblies with variable added damping is feasible and effective. Meanwhile, the simulation method used in this paper can obtain more precise approximation of the vibration of the core assembly and lays the foundation for more realistically simulating the seismic response of reactor core assemblies. It also helps to reduce the conservative margin of the structural design and is meaningful in engineering application. (authors)

Additional details

Publishing Information

Journal Title
Atomic Energy Science and Technology
Journal Volume
47
Journal Issue
8
Journal Page Range
p. 1356-1361
ISSN
1000-6931

Optional Information

Notes
7 figs., 3 tabs., 9 refs.