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Experimental Studies on Steel Corrosion in Lead-Bismuth with … · 2005. 2. 4. · Koji Hata,...

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INES-1#101 1 Experimental Studies on Steel Corrosion in Lead-Bismuth with Steam Injection Koji Hata, Kazuyuki Hara Nuclear Development Corporation Minoru Takahashi Research Laboratory for Nuclear Reactors Tokyo Institute of Technology
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  • INES-1#101 1

    Experimental Studies on Steel Corrosionin Lead-Bismuth with Steam Injection

    Koji Hata, Kazuyuki HaraNuclear Development Corporation

    Minoru TakahashiResearch Laboratory for Nuclear Reactors

    Tokyo Institute of Technology

  • 2

    Objectives

    BackgroundFeasibility study of Pb-Bi direct contact boiling water reactor (PBWFR) for innovated nuclear reactor energy system.PurposeTo investigate the compatibility of high Cr steel

    in the steam injecting Pb-Bi Study items

    Effectiveness of Cr contents for corrosion resistance Influence of (PH2/PH2O) ratio in the injecting steam

    on corrosion behaviorEffect of temperature on the steel corrosionSelection of more promising Cr steel and

    evaluation of its applicability

  • 3

    System of the Experimental Apparatus

    Pb-Bi Test Sub-systemSteam Supply Sub-system

    Pb-Bi drain tank

    Pb-Bitest tank

    vacuum pump

    exhaust gasheader

    cooling water

    DH meter

    gas bubbling

    flow meter

    pump

    filter

    pump

    waterconditioning

    tank

    condenser

    steamgenerator

    Ar gas

    H2 gas

    level sensorview port

    oxygen sensor

    chimney

    slug filter

    injection nozzle

  • 4

    Chimney

    Test Specimens

    Pb-BiCirculation

    Pb-Bi Test Tank

    Steam Bubbles

    Steam Injection Steam Exhaust

    Corrosion Test Concept

  • 5

    Chemical Composition of Tested Materials (wt.%)

    C Si Mn Ni Cr Mo W V Nb0.1 0.1 0.2 0.02 7.7 ~ 1.9 0.2 ~0.1 0.4 0.4 0.1 8.6 1.0 ~ 0.2 0.080.1 0.3 0.5 0.3 8.8 0.3 1.9 0.2 0.07

    0.15 0.1 0.5 0.6 10.0 0.5 ~ 0.2 ~0.1 0.3 0.5 0.2 12.0 1.1 1.0 0.3 0.10.1 0.3 0.5 0.3 12.0 0.3 1.9 0.2 0.05

    0.01 1.0 0.5 4.5 16.0 ~ ~ ~ 0.20.01 1.4 0.7 ~ 17.7 ~ ~ ~ ~

    F82HSTBA28

    RECLOY17-5PH

    Steel

    NF616TMK1

    HCM12HCM12A

  • 6

    Summary of the Experimental Parameters

    400 450 500O ~ ~O O O

    O ~ ~O ~ ~

    O : tested, ~ : not tested

    ExposurePeriods

    Oxygen Potential Relatives

    0.25 MPa 500 hours

    Temperatures (℃)

    5 x 10-6

    1 x 10-5

    DH

    500 ppb1,000 ppb

    1 x 10-6

    Pressuresin Test TankP H2/P H20

    < 3 x 10-7 < 30 ppb100 ppb

    P H2P H2O

    M H2O= (DH ) M H2 M H2O = molecular weight of H2O

    M H2 = molecular weight of H2

    (DH )=disolved hydrogen concentrationrelashionship between (P H2/P H2O) and DH

  • 7

    Oxygen Potential: Ox Electro-motive Force: Eand Oxygen Concentration: C

    Nernst’s equation for electro-motive force

    E = ( OREF – OPb-Bi )/nFwhere E: electro-motive force for an electrochemical system

    OREF : oxygen potential of reference electrode OPb-Bi : oxygen potential of Pb-Bi

    n: atomic valence of oxygen ion, F: Faraday’s constant

    Calculation of E for oxygen concentration of C

    E = [OREF - △GPb(Bi)-oxide - RTln(C/C0)] / nFwhere E: electro-motive force calculated for oxygen concentration of C

    △GPb(Bi)-oxide : Gibb’s free energy of formation for Pb(Bi)-oxideR: gas constant, T: temperatureC : oxygen concentration in Pb-Bi, C0 : oxygen solubility in Pb-Bi

  • 8

    Experimental Conditions for E, C, and T

    0

    100

    200

    300

    400

    500

    600

    250 300 350 400 450 500 550 600

    Temperature (℃)

    E(m

    V)

    Fe3O4 formation

    (Pb-Bi) oxide formation

    oxygen in Pb-Bi(wt.fraction)

    1.0E-10

    1.0E-11

    1.0E-9

    1.0E-8

    1.0E-7

    1.0E-6

    Experimental Condition

  • 9

    Fe in steel

    before exposure (Wa )

    Fe in steel

    O in Pb-Bi

    exposure in Pb-Bi

    Pb-Bi

    Fe

    (FeCr)3O4Fe3O4Pb-Bi

    Fe

    (FeCr)3O4Fe3O4Pb-Bi

    after exposure

    after exposure

    Fe

    (FeCr)3O4

    Fe3O4into Na

    Pb-Bi

    Na treatment (Wb)Fe

    (FeCr)3O4into

    citrate sol.

    citrate sol. Treatment (Wc)

    Process Flow for the Post-Exposure Treatment

  • 10

    Surface of HCM12A by Post-Exposure Treatment

    optical microscope

    4 mm4 mm 4 mm

    before exposure test Na-ethanol treatment citrate teatment

    before exposure test Na-ethanol treatment citrate teatment

    1,000μm1,000μm 1,000μm

    electron microscope

  • 11

    Fe

    (FeCr)3O4into

    citrate sol.

    Fe

    (FeCr)3O4

    Fe3O4into Na

    Pb-Bi

    Fe in steel

    before exposure (Wa ) citrate sol. Treatment (Wc )Na treatment (Wb )

    Fe3O4: defective(porous) structure

    (( (FeCr)3O4: sound structure

    Weight Changes after Na treatment : (Wb – Wa) after citrate treatment : (Wc – Wa)

  • 12

    Weight Changes after Na Treatment (400℃)

    -15.0

    -10.0

    -5.0

    0.0

    5.0

    10.0

    F82H

    STBA28

    NF616

    TMK1

    HCM12

    HCM12A

    17-4PH

    RECLOY

    Symbol of Steel (in the order of Cr content)

    Wb-Wa

    (mg/

    test

    pie

    ce)

    DH < 30 (ppb)

    DH = 100 (ppb)

    DH = 1,000 (ppb)

  • 13

    0

    50

    100

    150

    200

    250

    F82H

    STBA28

    NF616

    TMK1

    HCM12

    HCM12A

    17-4PH

    RECLOY

    Symbol of Steel (in the order of Cr content)

    Wa-

    Wc

    (mg/

    test

    pie

    ce)

    DH = < 30 (ppb)

    DH = 100

    DH = 1,000

    Weight Losses after Citrate Treatment (400℃)

  • 14

    0

    40

    80

    120

    160

    200

    F82H

    STBA28

    NF616

    TMK1

    HCM12

    HCM12A

    17-4PH

    RECLOY

    Symbol of Steel (in the order of Cr content)

    Wa-

    Wc

    (mg/

    test

    piec

    e)400℃

    450℃

    500℃

    Weight Losses after Citrate Treatment (DH=100 ppb)

  • 15

    Conclusions & Future Works

    Corrosion behaviors for some types of high Cr steel were examined.It was identified that :

    Higher Cr content lead more corrosion resistance to Cr steel, and more than 9 % Cr content would be feasible for an application.

    DH seemed to be little effective to control corrosion, but would be effective to avoid PbBi-slug formation or its precipitation.

    DH should be limited less than 1,000 ppb to lower the amountof corrosion product (Fe-oxide ) released in Pb-Bi.

    Corrosion rate increased with temperature, and Cr content effectiveness decreased at temperatures 500oC.

    Corrosion rate of 12Cr steel were estimated as a few μm /y at 400oCand evaluated to be promising for a large reactor structure.

    Further experiments are in progress to investigate the corrosion behavior of12Cr steel and other advanced materials (refractory metals and ceramics).


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