Published October 2020 | Version v1
Journal article

Correction of CPPF factor in QINSHAN CANDU reactor

Creators

  • 1. CNNP Nuclear Power Operations Management Co., Ltd., Haiyan (China)

Description

With the aging of the unit, the core fuel cooling performance of QINSHAN CANDU reactor decreases. To ensure the safe operation of the reactor, it needs to do regular analysis of ROP TSP. The analysis result is applied by correcting the CPPF which is used to calibrate ROP detectors to continuously track thermal hydraulic, pressure tube creep and other parameters. This paper focuses on the analysis of the ROP related parameters correction method for CPPF. Based on the actual operation data of unit 1, it analyzes the comparison of relevant parameters before and after correction, as well as the influence of operation such as refueling. Finally, it summarizes the operational optimization and countermeasure that can be taken. (author)

Additional details

Identifiers

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
41
Journal Issue
5
Journal Page Range
p. 8-11
ISSN
0258-0926

Optional Information

Notes
3 figs., 1 tab., 3 refs.; http://dx.doi.org/10.13832/j.jnpe.2020.05.0008