Cooperation on impingement wastage experiment of · PDF fileCooperation on impingement wastage...

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


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


L

Pressure measurement line

Injector

T/C line for water temp.

Target tube

T/C in Na

Injector

TEST UNIT AND EXPERIMENTAL CONDITIONS


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


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


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


Target tube experiment 1






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


Relation between wastage profile and intertube distance LExperiments conducted under similar conditions of T and water leak rate


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.


Thank you for your kind attention !


Control room of SWAT-1R (October 19, 2011)

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