Published October 2020
| Version v1
Journal article
Correction of CPPF factor in QINSHAN CANDU reactor
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
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 55086476
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CANDU TYPE REACTORS; REACTOR CHANNELS; THERMAL HYDRAULICS; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; FLUID MECHANICS; HEAVY WATER MODERATED REACTORS; HYDRAULICS; MECHANICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 3 figs., 1 tab., 3 refs.; http://dx.doi.org/10.13832/j.jnpe.2020.05.0008