Published June 2019 | Version v1
Journal article Metadata-only

Calculation Analysis of Response of Flow-Induced Vibration in Core Barrel for 1 : 5 Scale Model Test of HPR1000

Creators

  • 1. Mechanical Laboratory for Reactor Structure of Nuclear Power Institute of China, Chengdu (China)

Description

The analysis of the flow-induced vibration of internals for 1:5 scale model test of the Qinshan Nuclear Power Plant phase II was conducted by extrapolating from experimental data, to obtain the maximal response. The same method is used to get the response of the flow-induced vibration of core barrel for 1 : 5 scale model test of HPR1000. Firstly, the finite element model is established, and the proportion about the maximal response and the experimental data is obtained. Based on those proportions, the response can be achieved. (authors)

Additional details

Identifiers

DOI
10.13832/j.jnpe.2019.S1.0071;

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
40
Journal Issue
S1
Journal Page Range
p. 71-74
ISSN
0258-0926

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
54087846
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
DRILLING EQUIPMENT; EXPERIMENTAL DATA; FINITE ELEMENT METHOD; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; SCALE MODELS
Descriptors DEC
CALCULATION METHODS; DATA; ENRICHED URANIUM REACTORS; EQUIPMENT; INFORMATION; MATHEMATICAL SOLUTIONS; NUCLEAR FACILITIES; NUMERICAL DATA; NUMERICAL SOLUTION; POWER PLANTS; POWER REACTORS; REACTORS; STRUCTURAL MODELS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
2 figs., 3 tabs., 3 refs.; http://dx.doi.org/10.13832/j.jnpe.2019.S1.0071