Search


Information
ICMST-Tohoku 2018
Oct. 23 - 26, 2018
Sendai, Japan
ICMST-Shenzhen 2016
Nov 1 - 4, 2016
Shenzhen, China
(EXIT THIS PAGE)
ICMST-Kobe 2014
Nov 2(Sun) - 5(Wed), 2014
Kobe, Japan
Nuclear Regulation Authority Outline of the New Safety Standards for Light Water Reactors for Electric Power Generation
For Public Comment
Outline of New Safety Standard (Design Basis)
For Public Comment
New Safety Standards (SA) Outline (Draft)
For Public Comment
Outline of New Safety Standard(Earthquake and Tsunami)(DRAFT)
Issues
 

Vol.10 No.2(Aug)
Vol.10 No.1(May)
Vol.9 No.4(Feb)
Vol.9 No.3(Nov)

< Other Issues

 

Occasional Topics
OTjapan Measures for Tsunami Striking Nuclear Power Station in Japan
Special Article: The Great Tohoku Earthquake (1)
OTjapan The Tragedy of “To Be” Principle in the Japanese Nuclear Industry
EJAMOT_CN3_Figure1_The_outside_view_of_CEFR OTChinaPlanning and Consideration on SFR R&D Activities in China
< All Occasional Topics

Featured Articles
EJAM7-3NT72 A New Mechanical Condition-based Maintenance Technology Using Instrumented Indentation Technique
EJAM7-3NT73 Survey robots for Fukushima Daiichi Nuclear Power Plant

JSM
Contacts
(EJAM): ejam@jsm.or.jp
(JSM): secretariat@jsm.or.jp
HP: http://www.jsm.or.jp
(in English)

 
Vol.1 No.3 previous GA 8 - 9 - 10 - AA 10 - NT 14 - 15 - 16 - 17- 18 next Vol.2 No.1
Vol.1, No.4, NT14 EJAM (1-4-NT14) -Mitigation for Flow Accelerated Corrosion by Oxygenated Water Chemistry (OWC) in PWR Secondary Cooling System

Mitigation for Flow Accelerated Corrosion by Oxygenated Water Chemistry (OWC) in PWR Secondary Cooling System

 
The Japan Atomic Power Company (JAPC)
 

KEYWORDS:
Flow Accelerated Corrosion, OWC, Environmental Mitigation, ECP

 
1. Technical summary
 
Classification
(I: Inspection, II: Repair, III: Replacement, IV: Preventive Maintenance, V: Others(Operation Management))
 

Flow Accelerated Corrosions (FAC) have occurred on the inner surface of some carbon steel pipes of PWR secondary cooling system, and, therefore, they have been replaced with chromium-contained material pipes. Oxygenated Water Chemistry (OWC) is a promising environmental mitigation for FAC of carbon steel piping in PWR secondary cooling system. Condensate and feedwater systems are the most corrosive for FAC among single-phase flow systems in PWR secondary loop, because the magnetite film formed on the surface of the carbon steel has the maximum solubility at about 150ºC. Though high pH control by All Volatile Treatment (High AVT) is useful to suppress the whole surface corrosion in PWR secondary system, magnetite film created by high AVT has a limit to suppress the local corrosion such as FAC. Fig.1 shows an example of significant wall thinning even after High-AVT. Especially remarkable wall thinning occurred at position 5 and 4 of the upstream cross section A of the elbow due to the turbulence enhanced by an orifice located upstream as emphasized with pink color in Fig.1. OWC produces more defensive film of hematite on the surface of carbon steel and is effective to mitigate FAC.

A trial OWC was performed at feedwater system of Tsuruga Unit 2 (PWR, 1160MWe) in 2007. Fig.2 shows the trial OWC setup in secondary loop. Oxygen was injected at deaerator outlet. Shaded area with pink color in Fig.2 is the objective parts to suppress FAC by the trial OWC. Dissolved Oxygen (DO), Fe concentration and Electrochemical Corrosion Potential (ECP) were measured at some points as shown in Fig.2. Very small amount of injected oxygen could be considered to change the surface oxide film drastically from magnetite to hematite, based on an observation of ECP as shown in Fig. 3.

EJAM1-4-NT14_Fig.1_Change_of_wall_thickness_distribution_at_inlet_of_Elbow
Fig. 1 Change of wall thickness distribution at inlet of Elbow
EJAM1-4-NT14_Fig.2_Trial_OWC_setup_in_secondary_loop_of_Tsuruga_Unit_2

Fig.2 Trial OWC setup in secondary loop of Tsuruga Unit 2

EJAM1-4-NT14_Fig.3_Potential-pH_diagram_for_water-iron_system

Fig. 3 Potential-pH diagram for water-iron system

2. Scope

(1) Components
Piping in PWR secondary cooling system, e.g. condensate and feed water systems.

(2) Materials
Carbon steel

 
3. Features

(1) Very small amount of oxygen
Under high pH operation condition in PWR secondary cooling system, very small amount, below 5ppb in DO concentration, could suppress FAC.

(2) Fine Dissolved Oxygen Concentration Control
Dissolved oxygen (DO) Concentration in feed water system is well controlled to protect piping against FAC and avoid influence of DO on Steam Generator (SG) at the same time. Hydrazine is injected together with oxygen for this control purpose. Hydrazine reacts with oxygen moderately in feed water piping where the ratio of surface area to volume is small, but the reaction is accelerated in high-pressure feed water heater (HPH) where the surface area vs. volume ratio is large. As a result of this reaction control mechanism, DO concentration in feed water system is high enough in piping to protect FAC, and it is low enough to avoid influence on SG as shown in Fig.4.

?JAM1-4-NT14_Fig.4_Calculated_Oxygen_levels_along_feed_water_train

Fig.4 Calculated Oxygen levels along feed water train

4. Examples of Application
JAPC conducted trial OWC at feed water system of Tsuruga Unit 2. ECP measurement at inlet and outlet of high pressure feed water heater was also performed at this trial. The evaluation result shown in Fig.5 demonstrates that ECP (HPH) was remarkably raised by just a few-ppb oxygen injection. FAC rate and ECP were observed in FAC test loop under simulated AVT condition (180ºC, 5m/s, 500hr, pH9.2@ 25ºC. N2H4=0.1ppm). Demonstration ECP data at Tsuruga-2 showed good agreement with loop test data.
EJAM1-4-NT14_Fig.5_Behaviors_of_ECP_and_FAC_rate-as_a_function_of_DO_concentration

Fig. 5 Behaviors of ECP and FAC rate as a function of DO concentration

Fig.6 shows the results of DO concentration and ECP measurement during trial OWC at Tsuruga-2. DO concentration at Feed Water Booster Pump Outlet (FWBPO) was high enough to suppress FAC of piping, and that at HPH outlet was low enough to avoid influence on SG. Measured ECP at HPH outlet did not change after oxygen injection though that at HPH Inlet increased. This ECP behavior suggested that oxygen injected was consumed within HPH and did not transfer into SG.

Particulate Fe in feed water was sampled and analyzed at Tsuruga-2. As shown in Fig. 7, Fe oxide form was remarkably changed by OWC from magnetite to hematite in feed water system, but no change was observed at SG outlet. This result also shows the effectiveness of FAC suppression in feed water system piping and no influence on SG integrity.

EJAM1-4-NT14_Fig.6_Oxygen_and_ECP_behaviors_during_trial_OWC_at_Tsuruga-2

Fig.6 Oxygen and ECP behaviors during trial OWC at Tsuruga-2

EJAM1-4-NT14_Fig.7_Morphology_change_in_particulate_Fe_in_feed_water_at_Tsuruga-2

Fig.7 Morphology change in particulate Fe in feed water at Tsuruga-2

 
5. Reference
[1] W. Sugino et.al., Effect of Water Chemistry Improvement on Flow Accelerated Corrosion in Light-Water Nuclear Reactor, Asian Water chemistry Symposium 2009.
[2] H. Takiguchi, Oxygenated Water Chemistry for PWR Secondary System - New Approach to FAC -, NPC’08, Berlin, Germany, September 2008
 
6. Contact
Japan Society of Maintenology (ejam@jsm.or.jp)