Demonstration of Arrangement of on-Site Arrangment of Measurement Points for Flow Induced Vibration of HPR1000 Reactor Internals
- 1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu (China)
- 2. Reactor Engineering Research Institute, Nuclear Power Institute of China, Chengdu (China)
Description
In order to ensure the integrity of HPR1000 Reactor Internals (RI), on-site Flow induced vibration (FIV) measurement of RI should be performed in the hot functional test of unit 5 in Fuqing nuclear power plant which is the first reactor of HPR1000, and the arrangement of measure points should be demonstrated. RI structures and flow distribution of HPR1000 and M310 are compared in this paper. Based on the comparison, measurement points in new structures and weak locations in the same structures which need measurement are confirmed. Based on the analysis of HPR1000 RI scale model test results, the weak locations of FIV are found. The measurement of these weak locations will be critical and be arranged more measurement points in the actual measurement. For these weak locations, in case of the failure of some sensors, redundancy of measurement points in weak locations should be considered. Compared to the measurement of flow induced vibration in other reactor internals, the arrangement of the measurement points for flow induced vibration of HPR1000 reactor internals is reasonable. This plan was implemented in unit 5 of Fuqing Nuclear Power Plant. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 40
- Journal Issue
- S1
- Journal Page Range
- p. 55-58
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 54087842
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; DISTRIBUTION; FAILURES; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; REACTOR COMPONENTS; REDUNDANCY; SCALE MODELS; SENSORS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; EVALUATION; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; STRUCTURAL MODELS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 tabs., 4 refs.; http://dx.doi.org/10.13832/j.jnpe.2019.S1.0055