High-Temperature Electrochemical Corrosion Behavior of Fe-Cr-Ni Alloys in Simulated Pressurized Water Reactor Water

CORROSION ◽  
10.5006/2566 ◽  
2017 ◽  
Vol 74 (4) ◽  
pp. 415-423
Author(s):  
Le-fu Zhang ◽  
Jia-mei Wang
Keyword(s):  
High Temperature ◽  
Corrosion Behavior ◽  
Electrochemical Corrosion ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Reactor Water ◽  
Ni Alloys ◽  
Electrochemical Corrosion Behavior

Research on Corrosion Behavior of Copper in Reactor Thermal Hydraulic Test

2017 ◽  
Author(s):  
Haiyan Xu ◽  
Donghua Lu ◽  
Xiaohang Wu ◽  
Qianhua Su
Keyword(s):  
High Pressure ◽  
High Temperature ◽  
Corrosion Behavior ◽  
Electrochemical Corrosion ◽  
Severe Accident ◽  
Test Facility ◽  
Hydraulic Test ◽  
State Tests ◽  
Component Design ◽  
Electrochemical Corrosion Behavior

Safety instrument test facility (FITY) is one of the high temperature and high pressure test facilities in CGN. It is designed to conduct tests on thermal-hydraulic of safety system and instruments under the similar condition of reactor severe accident. FITY uses lot of copper components to realize sealing and insulation of vessel. Varies of hot state tests revealed that copper components worked well during the test, however, electrochemical corrosion was found as well, making water quality get worse. This article introduces chemical composition, physical properties and electrochemical corrosion behavior of copper component used in FITY, then analyzes the cause of corrosion and summarizes the notice for electronic component design under high temperature and high pressure conditions.

Simulated Environmental Tests for Selected ATF Cladding Solutions

2021 ◽  
Author(s):  
Sami Penttila ◽  
Juha-Matti Autio ◽  
Jari Lydman ◽  
Aki Toivonen ◽  
Seppo Peltonen ◽  
...  
Keyword(s):  
High Temperature ◽  
Base Material ◽  
Operating Conditions ◽  
Advanced Technology ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
High Temperature Furnace ◽  
Normal Light ◽  
C 30

Abstract Current development on advanced technology fuel (ATF) claddings is aiming at improved high temperature integrity of new cladding solutions that are based on the existing zirconium claddings. To assess their performance for commercial use, their thorough characterization is essential. The primary requirement for the cladding materials is the ability to tolerate loss of cooling for a significant period without failing. The tests in this work were performed on different types of coated Zr-alloys in a high temperature furnace in flowing steam conditions at 1100 °C/ 60 min, 1200 °C/ 30 min and 1300 °C / 5 min. In addition, exposures were performed in pressurized water reactor (PWR) water chemistry to confirm the material viability in normal light water reactor (LWR) operating conditions. After PWR and steam tests, the exposed specimens were studied using a Zeiss Crossbeam 540 field emission gunscanning electron microscope (FEG-SEM) equipped with a semi-quantitative energy dispersive X-ray spectrometer (EDS). Most of the tested specimens indicated detached coating layer. Varying amounts of cracking in the coatings were present. Some of the cracks extended into the base material. Based on this study, further development is needed.

Sign in / Sign up

Export Citation Format

Share Document