THE EFFECTS OF ZINC INJECTION FROM HOT FUNCTION TEST AT TOMARI UNIT 3 Presented by:Keisuke Sasaki Hokkaido Electric Power Co., Inc. 2014 ISOE Asian ALARA Symposium September 23-24,2014 1
THE EFFECTS OF ZINC INJECTION FROM HOT FUNCTION TEST AT TOMARI UNIT 3
Presented by:Keisuke Sasaki Hokkaido Electric Power Co., Inc.
2014 ISOE Asian ALARA Symposium September 23-24,2014
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Contents
- Introduction to TOMARI NPS - Zinc injection - Experiences of 1st cycle - Experiences of 1st refueling outage(RFO) - Experiences of 2nd refueling outage(RFO) - Conclusion
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Introduction to TOMARI NPS
Hokkaido
Japan
Letdown flow
Unit 1 Unit 2 Unit 3
Rated Electric Output
Reactor type Commercial Operation SG
579MW 579MW 912MW
PWR
1990
20m3/h
1992 2009
600TT 600TT 690TT
54m3/h
Unit1 Unit2
Unit3
3
Operated History of Unit 3
Introduction to TOMARI NPS
Unit 3
Output
2015 2014 2013 2012 2011 2010 2009 2008 2007 FY
1st CYCLE 378 days
2nd CYCLE 424 days
1st RFO 2nd RFO ▲HFT ▲Core loading
▲Commercial Operation
Zn injection
4
Zinc injection
Substitution of zinc for Co
Zinc injection during power operation
Suppression Co uptake into the inner oxide layer
Co
5
Zinc injection Zinc injection from HFT
Suppression Co uptake into the inner oxide layer
Corrosion suppression
Ni
Co
6
EXPERIENCES OF 1st CYCLE
0
5
10
0 50 100 150 200 250 300 350 400
Zn Concentration(
ppb)
Commercial Operation Time(day)
Control Band
Zinc concentration was controlled with the target concentration (5±3ppb).
Zn concentration in the primary coolant
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EXPERIENCES OF 1st CYCLE
Ni concentration was higher than that of the reference plant.
Ni concentration in the primary coolant
⇒ Ni releases from corrosion products and the base metal of SG tube.
0
0.5
1
1.5
2
0 50 100 150 200 250 300 350 400
Ni Concentration (ppb)
Commercial Operation Time (day)
Tomari 3
Reference
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EXPERIENCES OF 1st CYCLE
The Co-58 concentration was higher than that of the reference plant.
Co-58 concentration in the primary coolant
1E-2
1E-1
1E+0
1E+1
1E+2
1E+3
0 100 200 300 400
Co-58 Concentration (Bq/ml)
Commercial Operation Time(day)
Ion (Tomari 3) Ion (Reference)
Crud (Tomari 3) Crud (Reference)
⇒ Suppression Co uptake into inner oxide layer
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EXPERIENCES OF 1st RFO
1E+0
1E+1
1E+2
1E+3
1E+4
1E+5
1E+6
-24 0 24 48 72 96 120 144 168 192 216
Co-58 Concentration (Bq/ml)
Time from Shutdown (hr)
Ino (Tomari 3)
Ion (Reference)
Crud (Tomari 3)
Crud (Reference)
The particulate Co-58 was higher than that of the reference plant. The ionic Co-58 was at the same level as that of the reference plant.
Concentrations of radioactive Co-58(Ion,Crud) in the primary coolant
⇒ The amount of the corrosion product with a higher specific radioactivity has decreased.
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The amount of Ni removal was about 20% less than that of the reference plant.
EXPERIENCES OF 1st RFO
Tomari unit 3 Reference plant Ni(g) 3039 3639
Co-58(Bq) 1.3×1014 1.2×1014
Co-60(Bq) 8.0×1011 5.2×1011
Amount of Ni,Co-58,and Co-60 removal
The amount of Co-58 removal was about equal to that of the reference plant.
⇒ Corrosion suppression effect
⇒ Suppression Co uptake into the inner oxide layer and decreasing Ni inventory
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EXPERIENCES OF 1st RFO
The dose-rates at SG , RV inside and MCP were about over 40% less than those of the reference plant.
Dose-rates on SG tube, SG CH,RV Inside, and MCP
0
10
20
30
40
50
60
70
80
SG Tube SG CH Hot SG CH Cold RV Inside
Dose
Rat
e (
mS
v/h)
Reference
TOMARI 3
0
0.05
0.1
0.15
0.2
Hot Leg Cold Leg Crossover Leg
Dose
Rat
e (
mS
v/h)
Reference
TOMARI 3
⇒ The dose-rate reduction effect with zinc injection is about 40-60% at the 1st RFO.
TLD with Pb cover Ionization chamber
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Tomari unit 3 Reference plant
Co-58 inventory 22.2 43.2
Co-60 inventory 0.9 2.1
Radiation source inventory 24.2 48.1
EXPERIENCES OF 1st RFO
The Co-58, Co-60 and radiation source inventory were about 50% less than those of the reference plant.
Evaluation of Radiation Source Inventory [TBq]
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⇒ These are in good consistency with the actual dose-rates on the main components.
EXPERIENCES OF 2nd RFO
The dose-rates on SG tube, SG CH and RV Inside at the 2nd
RFO were about 50-60% less than those at the 1st RFO.
The dose-rates on MCP at the
2nd RFO were about 20-60% less than those at the 1st RFO.
0
0.01
0.02
0.03
0.04
0.05
Hot Leg Cold Leg Cross Over Leg
Dose
Rat
e (
mS
v/h)
1st RFO
2nd RFO
0
10
20
30
40
50
SG Tube SG CH Hot SG CH Cold RV Inside
Dose
Rat
e (
mS
v/h)
1st RFO
2nd RFO
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CONCLUSION
At the 1st RFO, the dose-rates at the main components are about 50% less than that of the reference plant,
as a similar trend to the radiation source inventory. Considerable dose-rate reduction at the 2nd RFO was
confirmed compared to the 1st RFO. From now on, further dose-rate reduction effect is
expected.
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Thank you for your Attention.