Some fundamental understandings of Zn-injection water chemistry on material corrosion in pressurized water reactor primary circuit
The optimization of water chemistry in pressurized water reactor (PWR) primary circuit is one of the most effective ways to achieve both safety and economy for operating PWR nuclear power plants (NPPs). Special attention has been paid to fundamental research and engineering application of Zn-injecti...
| Main Authors: | , , , , , |
|---|---|
| Format: | Article |
| Language: | English |
| Published: |
Elsevier
2022-06-01
|
| Series: | Corrosion Communications |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S2667266922000354 |
| _version_ | 1798032352066142208 |
|---|---|
| author | Xinqiang Wu Xiahe Liu Ziyu Zhang Jibo Tan En-Hou Han Wei Ke |
| author_facet | Xinqiang Wu Xiahe Liu Ziyu Zhang Jibo Tan En-Hou Han Wei Ke |
| author_sort | Xinqiang Wu |
| collection | DOAJ |
| description | The optimization of water chemistry in pressurized water reactor (PWR) primary circuit is one of the most effective ways to achieve both safety and economy for operating PWR nuclear power plants (NPPs). Special attention has been paid to fundamental research and engineering application of Zn-injection water chemistry (ZWC) in PWR primary circuit in recent years in China due to the rapid development of nuclear power. The present paper mainly reports the status of PWR NPPs in China and some fundamental understandings of ZWC on material corrosion. Effects of temperature (T), pH at T value, Zn concentration, Zn-injection sequence and lasting time on electrochemical corrosion behavior, oxide film characteristic and stress corrosion cracking (SCC) susceptibility of nuclear-grade austenitic alloys were investigated. A modified point defect model was used to discuss the effects of ZWC on the oxide films in high-temperature pressurized water. Some water chemistry parameters in PWR primary coolant system are proposed for mitigating corrosion and SCC of nuclear-grade austenitic alloys. |
| first_indexed | 2024-04-11T20:11:39Z |
| format | Article |
| id | doaj.art-587f5c80d6cf46719c29822894ad581b |
| institution | Directory Open Access Journal |
| issn | 2667-2669 |
| language | English |
| last_indexed | 2024-04-11T20:11:39Z |
| publishDate | 2022-06-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Corrosion Communications |
| spelling | doaj.art-587f5c80d6cf46719c29822894ad581b2022-12-22T04:05:05ZengElsevierCorrosion Communications2667-26692022-06-0165261Some fundamental understandings of Zn-injection water chemistry on material corrosion in pressurized water reactor primary circuitXinqiang Wu0Xiahe Liu1Ziyu Zhang2Jibo Tan3En-Hou Han4Wei Ke5Corresponding author.; CAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, ChinaCAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, ChinaCAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, ChinaCAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, ChinaCAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, ChinaCAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, ChinaThe optimization of water chemistry in pressurized water reactor (PWR) primary circuit is one of the most effective ways to achieve both safety and economy for operating PWR nuclear power plants (NPPs). Special attention has been paid to fundamental research and engineering application of Zn-injection water chemistry (ZWC) in PWR primary circuit in recent years in China due to the rapid development of nuclear power. The present paper mainly reports the status of PWR NPPs in China and some fundamental understandings of ZWC on material corrosion. Effects of temperature (T), pH at T value, Zn concentration, Zn-injection sequence and lasting time on electrochemical corrosion behavior, oxide film characteristic and stress corrosion cracking (SCC) susceptibility of nuclear-grade austenitic alloys were investigated. A modified point defect model was used to discuss the effects of ZWC on the oxide films in high-temperature pressurized water. Some water chemistry parameters in PWR primary coolant system are proposed for mitigating corrosion and SCC of nuclear-grade austenitic alloys.http://www.sciencedirect.com/science/article/pii/S2667266922000354Pressurized water reactorWater chemistryZinc-injectionMaterial corrosionStress corrosion cracking |
| spellingShingle | Xinqiang Wu Xiahe Liu Ziyu Zhang Jibo Tan En-Hou Han Wei Ke Some fundamental understandings of Zn-injection water chemistry on material corrosion in pressurized water reactor primary circuit Corrosion Communications Pressurized water reactor Water chemistry Zinc-injection Material corrosion Stress corrosion cracking |
| title | Some fundamental understandings of Zn-injection water chemistry on material corrosion in pressurized water reactor primary circuit |
| title_full | Some fundamental understandings of Zn-injection water chemistry on material corrosion in pressurized water reactor primary circuit |
| title_fullStr | Some fundamental understandings of Zn-injection water chemistry on material corrosion in pressurized water reactor primary circuit |
| title_full_unstemmed | Some fundamental understandings of Zn-injection water chemistry on material corrosion in pressurized water reactor primary circuit |
| title_short | Some fundamental understandings of Zn-injection water chemistry on material corrosion in pressurized water reactor primary circuit |
| title_sort | some fundamental understandings of zn injection water chemistry on material corrosion in pressurized water reactor primary circuit |
| topic | Pressurized water reactor Water chemistry Zinc-injection Material corrosion Stress corrosion cracking |
| url | http://www.sciencedirect.com/science/article/pii/S2667266922000354 |
| work_keys_str_mv | AT xinqiangwu somefundamentalunderstandingsofzninjectionwaterchemistryonmaterialcorrosioninpressurizedwaterreactorprimarycircuit AT xiaheliu somefundamentalunderstandingsofzninjectionwaterchemistryonmaterialcorrosioninpressurizedwaterreactorprimarycircuit AT ziyuzhang somefundamentalunderstandingsofzninjectionwaterchemistryonmaterialcorrosioninpressurizedwaterreactorprimarycircuit AT jibotan somefundamentalunderstandingsofzninjectionwaterchemistryonmaterialcorrosioninpressurizedwaterreactorprimarycircuit AT enhouhan somefundamentalunderstandingsofzninjectionwaterchemistryonmaterialcorrosioninpressurizedwaterreactorprimarycircuit AT weike somefundamentalunderstandingsofzninjectionwaterchemistryonmaterialcorrosioninpressurizedwaterreactorprimarycircuit |