Cooperation on impingement wastage experiment of Mod. 9Cr-1Mo steel using SWAT-1R sodium-water reaction test facility MARCH 6, 2013 FR13 International Conference Paris, France March 4-7, 2013 | F. Beauchamp a , M. Nishimura b , R. Umeda b , A. Allou a a CEA (French Alternative Energies and Atomic Energy commission), Nuclear Energy Directorate, Cadarache center, France b JAEA (Japan Atomic Energy Agency), Oarai R&D center, Narira, Oarai, Ibaraki, Japan 13 MARS 2013 | PAGE 1 CEA | 10 AVRIL 2012
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Cooperation on
impingement wastage experiment
of Mod. 9Cr-1Mo steel using
SWAT-1R sodium-water reaction
test facility
MARCH 6, 2013
FR13 International Conference
Paris, France
March 4-7, 2013 | F. Beauchampa, M. Nishimurab,
R. Umedab, A. Alloua
a CEA (French Alternative Energies and Atomic Energy commission),
Nuclear Energy Directorate, Cadarache center, France
b JAEA (Japan Atomic Energy Agency),
Oarai R&D center, Narira, Oarai, Ibaraki, Japan
13 MARS 2013 | PAGE 1CEA | 10 AVRIL 2012
CONTENT
Part 1
Context of the Program
Objectives and definition of the experiments
Part 2
Description of SWAT-1R test facility
Experimental conditions and test procedure
Part 3
Experimental results and discussion
Comparison with database and modelling
Part 4
Conclusion | PAGE 2CEA | MARCH 6, 2013
PART 1 – CONTEXT AND OBJECTIVES
13 MARS 2013
| PAGE 3
CEA | 10 AVRIL 2012
CONTEXT OF THE PROGRAM
13 MARS 2013 | PAGE 4CEA | MARCH 6, 2013
SODIUM
"Leaking" tube
STEAM
REACTION
PRODUCTS
LEAK HOLE
WASTAGE
"Target" tube
STEAM
WASTAGE
REACTIVE JET
SODIUM
WATER/STEAM
Schematic cross-section view
Leaktightness failure
↓
Na + H2O ���� NaOH + ½ H2
+ 162 kJ/mole (at 500°C)
STEAM GENERATOR (SG)
Example of impingement wastage profile
Why is the wastageimportant to study ?
Effect of a small leak from a SG tube
is impingement wastage on an
adjacent tube
Consequences are puncturing of the
“target” tube and then the risk of
propagation of leaks to other tubes
Knowledge of the wastage and leak
evolution rates is needed to insure the
safety actions by fast and improved
detection systems
Impingement wastage phenomenon is
very strongly correlated with the
nature of the tubes material
Wastage experiments data are needed
to quantify the wastage resistance
of materials
DEFINITION OF THE EXPERIMENTS
13 MARS 2013 | PAGE 5CEA | MARCH 6, 2013
Goal of the cooperation between JAEA and CEAImpingement wastage experiments performed in the sodium-water reaction test
facility (SWAT-1R) of JAEA Oarai R&D Center
6 pieces of straight tubes in T91 provided by CEA :
Modified 9Cr-1Mo (T91) steel is one of the material candidates of SGU
tubes for future sodium-cooled fast reactors (SFRs)
Need to expand the wastage database of the T91 steel
Leak conditions for the tests
3 tests at TNa=500°C - Psteam/water =18MPa
- leaks at the upper part of the SG
- penalizing events under 100%np
3 tests at TNa=350°C - Psteam/water=18MPa
- leaks at the lower part of the SG
- penalizing the response time of the
H2 detection system under 20%np
- no experiments performed before
at 350°CDistribution of SWAT-1R experiments versus T91 database as a function of
the sodium temperature and the water/steam leak rate
PART 2 – SWAT-1R TEST FACILITY AND
TEST PROCEDURE
13 MARS 2013
| PAGE 6
CEA | 10 AVRIL 2012
A P
Ar
Water holding pipe (WH)
Water Tank with heater
(WT)
Reaction products release Tank
(RT)
By-pass line
Relief line
R/D
Ar
SWAT-1R TEST FACILITY
13 MARS 2013 | PAGE 7CEA | MARCH 6, 2013DT sodium inventory: 0.8m3
RV sodium inventory: 0.4m3
Static Sodium heated to the
temperature of the test :
350°C or 500°C
Large injection leak rate > 10g/s
(with heater 350°C)
Small leak rate
< 10g/s
(no heater)
Test section
Sodium-Water Reaction Test Facility
Ar gas pressure monitoring line
1
[Upper view] [Lateral view]
Distance
Water injection tube
T/C
Target tube
Water injection tube
L
Pressure measurement line
Injector
T/C line for water temp.
Target tube
T/C in Na
Injector
TEST UNIT AND EXPERIMENTAL CONDITIONS
13 MARS 2013 | PAGE 8CEA | MARCH 6, 2013
Division wall
Center wall
Outer wall
Each target tube (T91 steel) in front of one water
injection tube
Experiments conducted in series over two days, one
target tube after the other
SWR confirmed by the rise of Tsodium (T/C)
Puncturing of target tube detected by the pressure fall of
argon
Operating conditions and parameters
Psteam/water (approx. 18MPa)
T steam/water in injection tube ~ Tsodium in RV
(approx. 350°C or 500°C)
Diameters of injector (mm) : 0.3, 0.4, 0.85 or 1.6
Intertube distances L : 8mm, 15mm or 17mm
27.80s
| PAGE 9CEA | MARCH 6, 2013
VIEW OF THE TEST SECTION
[Access view of water injection area]
Target tube
Water injection nozzle
T/C for reaction temp.
Target tube
Water injection tube
Ar gas pressure monitoring line
Water supply line
0
300
600
900
1200
0.0
5.0
10.0
15.0
20.0
-50 0 50 100 150
Tem
perature(C
)
Pressure (M
Pa)
Time(s)
PI-402 (×10)
P-806
TE-017 sodium
TE-018 sodium
Water injection time
34.35s0s
Water injection valves closeWater injection valves open
Penetration time 32.45 sec
| PAGE 10
Start of SWR
0.25 s
32.7 s
Sodium
temperature
TEST SEQUENCE : experiment 6
Water pressure in the injection tube
Puncturing of target tube CEA | MARCH 6, 2013
Target tube pressure
PART 3 – EXPERIMENTAL RESULTS
AND DISCUSSION
13 MARS 2013
| PAGE 11
CEA | 10 AVRIL 2012
EXPERIMENTAL RESULTS
13 MARS 2013 | PAGE 12CEA | MARCH 6, 2013
For all the experiments :
The target tube was punctured by impingement wastage
The penetration time was obtained
The wastage rate was determined :
WR =
The steam/water leak rate was known
No self-wastage was observed in any injector
of the injection tubes
2.2 (tube nominal thickness in mm)
Penetration time (second)
Target tubes after experiments 6,4 and 5
Orifice hole after experiment 1
Transition of water level meter during experiment 6
y = -2.608E-03x + 3.461E+00
R² = 9.974E-01
1.0
1.5
2.0
2.5
3.0
3.5
4.0
4.5
5.0
3.35
3.37
3.39
3.41
3.43
3.45
3.47
3.49
3.51
3.53
-10 0 10 20 30 40 50
SS(V
)
Level m
eter output (V
) (corelated value)
Time(s)
Water injection valve open
Water injection valve close
IMPINGEMENT WASTAGE RESULTS
13 MARS 2013 | PAGE 13CEA | MARCH 6, 2013
Target tube experiment 1
Target tube experiment 2
Target tube experiment 3
Target tube experiment 5
Target tube experiment 6
Target tube experiment 4
High temperature ⇒ high wastage rate
Wastage type (toroidal or pit) is dependent on intertube distance L,
water/steam leak rate and the shape of the SWR jet
Wastage rates at higher temperature 500°C are much more sensitive to the variations
of the test parameters than those at 350°C
DISCUSSION
13 MARS 2013 | PAGE 14CEA | MARCH 6, 2013
Relation between wastage profile and intertube distance LExperiments conducted under similar conditions of T and water leak rate
13 MARS 2013 | PAGE 15CEA | MARCH 6, 2013
Comparison of experimental results with database and modelling
DISCUSSION
Wastage rates from Experiments 4, 5 and 6 (500°C) are in good coherence with the
wastage test database (Mod 9Cr 1Mo steel)
Good correlation between the wastage rates predicted by the CEA modelling and
those obtained for the 3 experiments at 500°C
for 9Cr steel - 480-510°C - P>13 MPa
for 9Cr steel - 500°C - 18 MPa
PART 4 – CONCLUSION
13 MARS 2013
| PAGE 16
CEA | 10 AVRIL 2012
CONCLUSION
6 experiments were carried out in the SWAT-1R facility of JAEA Oarai R&D Center to
study the wastage resistance of the Mod. 9Cr-1Mo steel (T91) straight tubes.
These experiments were performed under the cooperation between CEA and JAEA.
The experiments were conducted successfully:
all the tubes were punctured by the reaction jet,
wastage and steam/water leak rates were obtained,
experimental results brought some new determining sets of wastage data on T91.
This fruitful cooperation has contributed to:
expanding the wastage database on T91,
upgrading wastage rates prediction from modelling,
the safety demonstration of future steam generators units.