Atucha-2 PHWR Three Dimensional Neutron Kinetics Coupled Thermal-hydraulics Modelling and Analyses

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    UNIVERSITÀ DI PISAUNIVERSITÀ DI PISADIPARTIMENTO DI INGEGNERIA MECCANICA,DIPARTIMENTO DI INGEGNERIA MECCANICA,

    NUCLEARE E DELLA PRODUZIONENUCLEARE E DELLA PRODUZIONEVIA DIOTISALVI 2, 56100 PISAVIA DIOTISALVI 2, 56100 PISA

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    Atucha-2 PHWR threeAtucha-2 PHWR three

    dimensional neutron kineticsdimensional neutron kinetics

    coupled thermal-hydraulicscoupled thermal-hydraulics

    modelling and analyses by themodelling and analyses by theRELAP5-3!RELAP5-3!

    "# Parisi$"# Parisi$ A# el %e&o$A# el %e&o$ '# (a))antini$ *#'# (a))antini$ *#

    +Auria$ ,# &ano&+Auria$ ,# &ano&

     RELAP5-3 .ser /eminardaho .ni&ersity "ampus$ daho *alls$ ./A

    01-2 %o&ember 21

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    RELAP5-3D User Seminar – Idaho University Campus, Idaho a!!s, USA – "ovem#er $%-&', &''% &

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    Outline Introduction

    Atucha II PHWR Features

    280 channels TH model

    HELIOS CrossSections Li!raries

    "# $% TH model

    Sam&le results

    Conclusions

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    RELAP5-3D User Seminar – Idaho University Campus, Idaho a!!s, USA – "ovem#er $%-&', &''% 3

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    Introduction Ar'entinean electric utilit( )$ucleoelectrica

    Ar'entina * Societad Anonima+ ,$ASA- si'ned ana'reement .ith the San Piero a /rado $uclearResearch /rou& ,/R$SP/- o the 1niersit( o Pisa ,1$IPI- in 2003 or the deelo&ment o adancedsimulation models or the AtuchaII $PP

    /R$SP/41$IPI deelo&ed hermal-hydraulics5%eutronics5 "* and /tructural (echanics models or the saet( anal(sis o the &lant

    Currentl( /R$SP/41$IPI is also assistin' $ASA inthe deelo&ment o the "hapter 05 o the */AR

    6estEstimate Plus 1ncertaint( ,6EP1- method&ursued or licensin' calculation  deelo&ment o a6E RELAP7"# model or licensin' anal(ses

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     Atucha II PHWR Features AtuchaII is a 92 :We Siemens desi'ned PHWR under construction in

    Lima5 Ar'entina

    Constructions started in ;98;5 sus&ended in ;99<

    Constructions resumed in 20075 =rst criticalit( scheduled or 20;0

    Hea( .ater cooled5 hea( .ater moderated PWR

     1ni>ue eatures?

    Primar( circuit !ased on the %onoiPWR desi'n Circuit or moderator coolin' 4 FW &reheatin'

    $atural 1ranium uel

    @ertical Fuel Channels

    Lar'e RP@ ,3" meter internal diam-

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     Atucha II PHWR Features Primar( circuit characteristics B con='uration

    2 1Tu!es S/5 2 :CP

    Primar( side &ressure? ;;7 :Pa

    Primar( side tem&eratures? 238 C at RP@ inlet5 ";""C at RP@ outlet

     Total thermal &o.er transerred to the steam .ater c(cle ? 2;3< :W

    Aera'e :oderator Tem&erature? ;30 C

    < 1Tu!es HD or :oderator coolin' 4 FW &reheatin'

    (oderator "ooling"ircuit

    Primary "ircuit

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     Atucha II PHWR Features Fuel &laced in ue CRs

    "R layout

    *uel Element

    RP4 Layout

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     Atucha II PHWR Features Emer'enc( 6oron Inection S(stem desi'ned to act durin' RIA ,e'5

    L6LOCA-

     To counteract &ositie reactiit( ecursion due to the reactor &ositie oidcoeGcient

    < Lances inect hi'h &ressure solution o !oric acid into the moderatortan

    S(stem reaction time reduced !( $ASA to rou'hl( 07 secs

    oronn6ection

    Lance 70 o8 9:

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    Rationale for the Nodalization

    Structure $odaliation is the result o a !rainstormin' &rocess .here thecom&utational resources aaila!le and the e&erience o the user&la( a maor role consistentl( .ith the o!ecties o the anal(ses

    Selected code .as RELAP7"#J deelo&ed or industrial

    a&&lications in 1S5 inde&endent rom the code,s- used !( the

    re'ulator

    %e( role o?

    :aimum allo.ed num!er o nodes5

    :aimum alloca!le com&utercode memor(

     T(&icalit( o the accident scenarios to !e anal(ed

    DEGB LBLOCA – Initial Reactivity Excursion and Recovery

    LBLOCA and other transients

    1ser in su&&l(in' unaaila!le inormation

    Proidin' suita!le >uali=cation

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    Rationale for the Nodalization

    Structure )280 channels nodaliation+ consistent .ith thet(&icalit( o the accident scenarios to !e anal(ed,e' #E/6 L6LOCA * Initial Reactiit( Ecursionand Recoer(-

    Com&uter resources not suGcient to im&lement allC$A2 ECCS and Lo'ics

    )0 channels nodaliation+ consistent .ith thet(&icalit( o the accident scenario ,e' L6LOCAand other transients-

    Code com&uter resources saturated !(

    im&lementation o suita!le ECCS and Lo'ics5 so? )280 channels nodaliation+  or "# $% * TH anal(ses

    )0 channels nodaliation+  or 0# $% * TH anal(ses

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    50°

    CL axisHL axis

    CL !L

    CL"!L"

    DC Nodalization & RPV Syetry

    Due to the le#s #eo$etry not all the

    coolant co$in# %ro$ a loo& exits %ro$

    the sa$e loo&' A $ixin# ()et*een

    inlet and outlet+ has to )e ta,en into

    account

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    DC Nodalization !Hydraulics"

    - vertical (do*n*ard oriented+ &i&es

    axially su)divided in "5 volu$es

     .oined )y cross/%lo* ($ulti&le+ .unctions

    (co$&onent no' in the le%t %i#ure+

    - )ranches re&resent the u&&er &art1 t*o

    o% the$ lin,ed to the CL

    DC/23 )y&ass connection

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    #P Nodalization

    4hree layers

    + Botto$ &art – hori6ontally oriented (red+ Level/ (L+

    "+ Botto$ &art u& to the channel inlet – vertically oriented (#reen+ Level/" (L"+

    7+ Channel inlet u& to the lo*er %ace o% core &late – vertically oriented ()lue+

      Level/7 (L7+

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    #P Nodalization

    L3 #rid nodali6ation a&&roach

    8ive rin#s are identi%ied containin# an

    9entire: nu$)er o% )oxes

    "

    7

    ;

    5Withouth!""#$ i"$#t%&

    CL1 'L1

    CL2'L2

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    #P NodalizationL3 #rid nodali6ation a&&roach

    7- sectors (a$&litude o% each sector is

    0° < =$axi$u$ co$$on divisor> %or

    ?0°1 ;0° and 50°+ divide the )oxes into

    "00 &arts (su)/)ox+ re&resented )y

    "00 9)ranches:

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    #P NodalizationBottom partBottom part

    5 radial rin#s (accordin# to L3 &late su)division+

    - a6i$uthal &arts (accordin# to DC su)division+

    "5 hori6ontal 9)ranches: constitutethe )otto$ L3

    4he external rin# is connected to

    DC &i&es (#reen circles+

    Each hor' )ranch is connected to

    the vert' )ranches %or$in# the L3

    #rid (red circles+

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    Core channels Nodalization8ive throttle ty&es

    Green 6one Blue 6one "

    Red 6one 7

    Blac, 6one ;

    Li#ht )lue 6one 5

    Considering

    -5 Boxes

    7- Radial

    sector 5 Rin#s

    @ax &o*er  channel

    "0

    euivalent

    channels

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    $P Nodalization

    8our layers+ 8irst hori6ontal &art connected to the coolant channel outlets ()lue+

    "+ 8irst vertical &art u& to the !L axis (oran#e+

    7+ econd hori6ontal &art alon# the !L (#reen+

    ;+ econd vertical &art to account %or the nearly se$is&herical

      sha&e (yello*+

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    $P Nodalization

    4he three di%%erent layers$odelled )y several )ranches

    E'#'1 the %irst layer – hori6ontal

    "5 9)ranches: connected to the

    "0 euivalent core channel

    (red circles+

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        G   r   u   p   p   o    R

        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o   a

        G   r   a    d   o

        G   r   a    d   o

    RPV Nodalization

    Not !$$ h!""#$%(#)(#%#"t#*&

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        G   r   u   p   p   o    R

        i   c   e   r   c   a    N   u   c    l   e

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        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o   a

        G   r   a    d   o

        G   r   a    d   o

    #OOP Nodalization !includin%

    S"9tandard: nodali6ation techniueGeneral rules %ollo*ed  .unction only connected to a &i&e Ratio len#th o% t*o consecutive nodes

    stays *ithin 0'5 – "'0 unction at inlet and outlet o% nodes only

     G $odeled till the isolation valves

    3u$& ho$olo#ous curves ta,en %ro$ FA/A nodali6ation

    2 $oo)% +o*#$#*1 $oo) (#)(#%#"t#*

  • 8/17/2019 Atucha-2 PHWR Three Dimensional Neutron Kinetics Coupled Thermal-hydraulics Modelling and Analyses

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        G   r   u   p   p   o    R

        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o   a

        G   r   u   p   p   o    R

        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o   a

        G   r   a    d   o

        G   r   a    d   o

    'oderator syste

    $oo)% +o*#$#* - 1 $oo) (#)(#%#"t#*

    '#!t #.h!"/#(%P(i+!( %i*# o

    +o*#(!to( oo$#(

    S!#t i"#tio"

    Mo*#(!to(

    )u+)

    Mo*#(!to(*o3"o+#(

    S!#t i"#tio" )o(t

    Pump homologous curves given by NA-SA

  • 8/17/2019 Atucha-2 PHWR Three Dimensional Neutron Kinetics Coupled Thermal-hydraulics Modelling and Analyses

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    RELAP5-3D User Seminar – Idaho University Campus, Idaho a!!s, USA – "ovem#er $%-&', &''% &&

        G   r   u   p   p   o    R

        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o   a

        G   r   u   p   p   o    R

        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o   a

        G   r   a    d   o

        G   r   a    d   o

    Neutron (Sec #i)raries odel * eneration

    ENDF/B-! N"#$N"#$%ulti& 'Sec

    ()* &roups+

    ,E!#S,E!#S

    v. .0v. .0

    'Secs ibraries'Secs ibraries

    (1 &roups+(1 &roups+

    1D 2ransport

    Calculations

  • 8/17/2019 Atucha-2 PHWR Three Dimensional Neutron Kinetics Coupled Thermal-hydraulics Modelling and Analyses

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    RELAP5-3D User Seminar – Idaho University Campus, Idaho a!!s, USA – "ovem#er $%-&', &''% &3

        G   r   u   p   p   o    R

        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o   a

        G   r   u   p   p   o    R

        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o   a

        G   r   a    d   o

        G   r   a    d   o

    Neutron (Sec #i)raries Code Adanced lattice &h(sics code HEL'/HEL'/ used to calculate the cross

    section sets

    HEL'/HEL'/ is a neutron and 'amma trans&ort code or lattice !urnu&5 in'eneral t.odimensional 'eometr(

    #eelo&ed !( /./4, /./4, 

    ;;

     /candpo

  • 8/17/2019 Atucha-2 PHWR Three Dimensional Neutron Kinetics Coupled Thermal-hydraulics Modelling and Analyses

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        i   c   e   r   c   a    N   u   c    l   e

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        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o   a

        G   r   a    d   o

        G   r   a    d   o

    Neutron (Sec #i)raries odel Channel!(channel !urnu& distri!ution su&&lied !( $ASA

  • 8/17/2019 Atucha-2 PHWR Three Dimensional Neutron Kinetics Coupled Thermal-hydraulics Modelling and Analyses

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        G   r   u   p   p   o    R

        i   c   e   r   c   a    N   u   c    l   e

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        P    i   e   r   o   a

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        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o   a

        G   r   a    d   o

        G   r   a    d   o

    Neutron (Sec #i)raries odel *or e&ery composition a cross section set is generated

    Each "ross /ection set contains tables 8or>

    Fast and Thermal #iMusion CoeGcients

    Fast and Thermal Ca&ture Cross Sections

    Fast and Thermal Fission Cross Sections

    Fast and Thermal $uFission Cross Sections

    Remoal Cross Sections ,/rou& ;  2-

    Inerse $eutron @elocities

    Assem!l( #iscontinuit( Factors ,A#Fs-

    Photoneutron eMect ,su&&lied !( $ASA- to !e taen into account

    directl( in $ESTLE in&ut

    N (S #i) i d l

  • 8/17/2019 Atucha-2 PHWR Three Dimensional Neutron Kinetics Coupled Thermal-hydraulics Modelling and Analyses

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        G   r   u   p   p   o    R

        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o   a

        G   r   u   p   p   o    R

        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o   a

        G   r   a    d   o

        G   r   a    d   o

    Neutron (Sec #i)raries odel Seeral HEL'/HEL'/ in&ut decs deelo&ed?

    Fuel Channel ,hea'onal lattice- Fuel Channel N :oderator

    CR a!sor!ers ,!lac B 're( CR5 u&&er B lo.er &art-

    ReKector? Radial5 6ottom5 and To&

    8uel Channel 8uel Channel Re%lector 8uel Channel CR

    N (S #i) i d l

  • 8/17/2019 Atucha-2 PHWR Three Dimensional Neutron Kinetics Coupled Thermal-hydraulics Modelling and Analyses

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        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o   a

        G   r   a    d   o

        G   r   a    d   o

    Neutron (Sec #i)raries odel

    Inter&olation in Fie#imensional Ta!lesInter&olation in Fie#imensional Ta!les

    For C$AII core model FieFie Inde&endent Parameters .ill !e

    used?

    ;- Fuel Tem&erature ,#o&&ler Feed!ac-

    2- Coolant #ensit( ,@oid EMect-

    "- Coolant Tem&erature

  • 8/17/2019 Atucha-2 PHWR Three Dimensional Neutron Kinetics Coupled Thermal-hydraulics Modelling and Analyses

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        P    i   e   r   o   a

        G   r   u   p   p   o    R

        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o   a

        G   r   a    d   o

        G   r   a    d   o

    Cross Section 'odellin%

     A42C!ACRO'exe

    (8OR4RAF ?0 &ro#ra$+

    3e4erence

    Cross Section

    alues

    C3#SS

    SEC2!#N

    !B3A3!ES(nemtab5 nemtabr65

    nemtabr615 nemtabr675

    nemtabr6)+

    Cross-Section

    ariation

    Coe44icients

    5D LINEAR

    INTERPOLATION ROUTINE 

    (LINT5D)

    LEAST SQUARE 

    METHOD(MC)

    ?ref 

    Coolant  ρ ∂

    Σ∂

     Moderator  B∂

    Σ∂

     Fuel T ∂

    Σ∂

     Moderator T ∂

    Σ∂

    Coolant T ∂

    Σ∂

    C S i ' d lli

  • 8/17/2019 Atucha-2 PHWR Three Dimensional Neutron Kinetics Coupled Thermal-hydraulics Modelling and Analyses

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        G   r   u   p   p   o    R

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        P    i   e   r   o   a

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        i   c   e   r   c   a    N   u   c    l   e

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        P    i   e   r   o   a

        G   r   a    d   o

        G   r   a    d   o

    Final @ersion o theAT1CHACROSS &ro'ram

    5 lines Fortran&ro'ram

    Automaticall( &erorm

    adhoc inter&olations5

    or seeral ones o thereactor core

    @ariation coeGcientcalculation

    $ESTLE in&ut .ritin'

    Cross Section 'odellin%

    ?ref 

    Coolant  ρ ∂

    Σ∂

     Moderator  B∂

    Σ∂

     Fuel T ∂

    Σ∂

     Moderator T ∂

    Σ∂

    Coolant T ∂Σ∂

    CR in%or$ation

    (4y&e1 an#les1 nu$)er+

    FE4LE IF324

    +D N, .H l d d l

  • 8/17/2019 Atucha-2 PHWR Three Dimensional Neutron Kinetics Coupled Thermal-hydraulics Modelling and Analyses

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       a   r   e    S .

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        P    i   e   r   o   a

        G   r   a    d   o

        G   r   a    d   o

    +D N, - .H cou/led odel "# $% nodes o!tainin' ).ei'hted+ eed!ac rom TH model

    $ESTLE sendin' !ac &o.er distri!ution to FA heat structures

    Po.er

    %E/LE%E/LE

    Fuel Channel

     TH model

    :oderator

     TH model

    Coolant#ensit(

    Coolant Tem&erature

    :oderator Tem&eratur

    e

    6oronConcentrati

    on

    Fuel Tem&eratur

    e

    RELAP5-3RELAP5-3

    +D N t ,i ti d l

  • 8/17/2019 Atucha-2 PHWR Three Dimensional Neutron Kinetics Coupled Thermal-hydraulics Modelling and Analyses

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        P    i   e   r   o   a

        G   r   u   p   p   o    R

        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

    +D Neutron ,inetic odel $ESTLE "# $% model characteristics?

    Hea'onal lattice "'"; c$ &itch

    ;0 aial la(ers or actie core? 7"03 cm

    ; la(er or the 6ottom ReKector?

  • 8/17/2019 Atucha-2 PHWR Three Dimensional Neutron Kinetics Coupled Thermal-hydraulics Modelling and Analyses

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        G   r   u   p   p   o    R

        i   c   e   r   c   a    N   u   c    l   e

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        P    i   e   r   o   a

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        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

    CR odelin% ;8 Control Rods

    inserted dia'onall(,;327-

    6lac CR Haniuma!sor!er

    /re( CR  Steela!sor!er

    Each CR has upper and lo

  • 8/17/2019 Atucha-2 PHWR Three Dimensional Neutron Kinetics Coupled Thermal-hydraulics Modelling and Analyses

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        P    i   e   r   o   a

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       a   r   e    S .

        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

     

    88   ))   /9 8

    )):

    )70

    /*9

    /:

    :0

    :9

    CR odellin% Four Cross Sections Li!raries calculated or CR modellin'

    CR DSec corrections due to the "# 'eometr( eMects introduced usin' "#:C$P7 :onte Carlo Simulations 

    88   ))   /9 8

    )):

    )70

    /*9

    /:

    :0

    :9

    CR and Fuel Channels Section NESTLE modelling

    +D N, .H l d d l F l Ch l

  • 8/17/2019 Atucha-2 PHWR Three Dimensional Neutron Kinetics Coupled Thermal-hydraulics Modelling and Analyses

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       a   r   e    S .

        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

    +D N, - .H cou/led odel - Fuel Channels

    Atucha II $PP 280 channel280 channel RELAP7"# TH model used

    o TH channels modeled B cou&led accordin' to?

    H(draulic characteristics ,throttled t(&e4unthrottled-

    Rom!oidal su!&lena !elon'in'

    Po.er distri!ution

     Transient t(&e

    Code resources0 0" 07 0; 05 0- 0 0 0? 0 " 7 ; 5 - ? "0 " "" "7 "; "5 "- " " "? 70 7 7" 77 7; 75 7- 7 7 7? ;0 ; ;" ;7 ;; ;5

    BGB8

    BE

    BD

    BC

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     AH

     A!

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     A8

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    " "

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    " " 7 7 " "7 7 7 7

    "

    " " " 7

    7 7 " "7 7 7 7

    " " 7 7 7 7

    - " " "; 7 7 7; ; ; ;- 7 7 7 " "

    7 " " ; ; 7 7; ; ; ;

    " " 7 7 7 ; ;

    7 7 7 "; ; ; ;; ; ; ;

    7 -

    " " 7 7 7 ;

    ; ; ; 7; ; ; ;; ;

    " - 7 7 ;

    ; 7 7 "5 ; ; ;; ; 5 5

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    " " 7 7 ; ;

    7 7 7 "5 ; ; ;; 5 5 5

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    " " 7 7 7 ; ;

    ; 7 7 "5 5 ; ;; 5 5 5

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    " " 7 7 ; ;

    ; 7 7 75 5 ; ;; ; 5 5

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    " " 7 7 7 ;

    ; 7 7 "5 ; ; ;; ; 5 57 7 ; ; "

    - " ; ; 7 7; ; ; ;; ; ; ; - 7 7

    7 " " ; ; 7 7; ; ; ;7 ; ; ; " 7 7

    " " 7 7 7 7; ; ; ;

    " " 7 7 7 7 ; ;

    - " " ; 7 7 7; ; ; ;- 7 7 7 " " "

    " 7 7 7 "7 7 7 7

    " " " 7 7 7

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    " " " " 7 7 7

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    7 7 7 7

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  • 8/17/2019 Atucha-2 PHWR Three Dimensional Neutron Kinetics Coupled Thermal-hydraulics Modelling and Analyses

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       a   r   e    S .

        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

    +D N, - .H cou/led odel - Fuel Channels

    280 RELAP7 Fuel Channels cou&led .ith

  • 8/17/2019 Atucha-2 PHWR Three Dimensional Neutron Kinetics Coupled Thermal-hydraulics Modelling and Analyses

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        G   r   u   p   p   o    R

        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o   a

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        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

    +D N, - .H cou/led odel - +D 'oderator tan0 

    :oderator :odel usin' RELAP7"# "# com&onents 

    &ossi!ilit( to simulate .ith hi'h de'ree o realism the !oron clouds calculated !(

    CF# simulation o as(mmetric transients

    @er( so&histicated ma&&in' scheme resulted rom the use o C(lindrical "# THCom&onents cou&led .ith Hea'onal $% cells

    Q  radial sectors radial sectors

    Q 0B 0 B 0 C 02 aDial layers 8or0B 0 B 0 C 02 aDial layers 8or

    ottom Reector$ "ore Acti&e )one$ottom Reector$ "ore Acti&e )one$

    op reectorop reector

    Q 0 a)imuthal sectors0 a)imuthal sectors3 (oderator ank F%E/LE mesh o&erlay

    'odellin% the )oron eer%ency in1ection

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    RELAP5-3D User Seminar – Idaho University Campus, Idaho a!!s, USA – "ovem#er $%-&', &''% 3*

        G   r   u   p   p   o    R

        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

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        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

    'odellin% the )oron eer%ency in1ection

    syste 6oron Inection Clouds calculated !( a &reious CF#

    CFD T: 

    code calculation

     reconstructed !( adhoc T:#P1$ com&onents in the "# :oderator Tan

     Inection onesInection ones

     Com&arison CF# * RELAP7"#Com&arison CF# * RELAP7"#

    inected mass o !oroninected mass o !oron

    RELAP7"# :ass o !oronRELAP7"# :ass o !oron

    distri!ution in diMerent la(ersdistri!ution in diMerent la(ers

    2345 Channels6 Nodalization Resources

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        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

    345 Channels Nodalization Resources

    $um!er o H(draulic $odes? 753

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       a

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        i   c   e   r   c   a    N   u   c    l   e

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        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

    +D N, Cou/led .H SS Results

     Core SS conditions?

    Hot Full Po.er? 2;0 /W

    $ominal alues or Fuel5 Coolant and :oderator Tem&eratures distri!ution

    CR in ,$ASA con='uration-

    G0 ?; in

    G"0 - in

    G70";'5 in

    0 ;'"? in

    hut/O%% ("0 70+ All Rods Out

    6oron Concentration? 007 &&m

    SS Radial Po7er

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        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

    SS - Radial Po7er %eM 099770

    F( ;"8

    :aimum:aimum

    :in ;0; :W:in ;0; :W

    :a 7 :W:a 7 :W

    :inimum

    SS Radial Po7er

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        P    i   e   r   o

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       a   r   e    S .

        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

    SS - Radial Po7er

    Radial Po.er ? S&atial Form Function

    SS Noralized Reactor A8ial Po7er

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        i   c   e   r   c   a    N   u   c    l   e

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        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

    SS Noralized Reactor A8ial Po7er

    ADial Po

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       a   r   e    S .

        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

     Fuel Channels 'ass Flo7:ass Flo. &er Assem!l( %'4sU

    SS Cou/led Codes .H

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       a   r   e    S .

        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

    SS Cou/led Codes .H

    ParaetersAll the main TH &arameters coner'ed to SSreerence aluesE'5 moderator Tan tem&erature distri!ution

    Botto$ 4o& Re%lector 

     Active Core

    #9#OCA 5 ;A in C#3 Sa/le Results

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        G   r   u   p   p   o    R

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        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

    L6LOCA 0; A in CL2 ,reerence #6A or Atucha2-

    Actuation oScram !( all CRs ? N003 s

    Emer'enc( 6oron Inection S(stem ? N 0" s

    :CP; B 2 rundo.n ? N003 s

    CR com&letel( inserted ? N"< s

    End o 6oron Inection in moderator tan ? N"9; s

    %o /a8ety threshold eDceeded

    #9#OCA 5:;A in C#3 - Sa/le Results

    #9#OCA 5 ;A in C#3 Sa/le Results

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        G   r   u   p   p   o    R

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        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

    #9#OCA 5:;A in C#3 - Sa/le Results

    Reactor Po.erReactor Po.er Pressure Trends in 1P andPressure Trends in 1P and

    PRPR

    Fuel Clad Tem& in Central and Hot ChannelFuel Clad Tem& in Central and Hot Channel@oid Fraction in Central and Hot@oid Fraction in Central and Hot

    ChannelChannel

    'CP Shaft seizure Sa/le Results

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       a

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        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

    'CP Shaft seizure - Sa/le Results

    :CP2 Shat seiure in ; s

    :CP; continues o&eration

    CRs scram? N0; s

    CRs com&letel( inserted? N"3" s

    %o /a8ety threshold eDceeded Reactor Po.erReactor Po.er

    @oid Fraction in Central B Hot@oid Fraction in Central B Hot

    ChannelChannel

    : /.: 1.: 7.: ).: ;.: 8.: *.: 9.: 0.: /:.:

    2ime (s+

    -./:

    :

    ./:

    .1:

    .7:

    .):

    .;:

    .8:

         o

       i   d

       F  r  a  c   t   i  o  n

    JinGra% ;' / 0"/"-/"00A

    KKK   @C3Lha%tLei6ure void#"500;0000

    K K K K K K K K K K K K K K K K K

    MM M   @C3Lha%tLei6ure void#"500A0000

    M M M M M M M M M M M M M M M M M

    NNN   @C3Lha%tLei6ure void#"50"0000

    N

    N

    N

    N

    N

    N

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    N   N

    N

    N

    N

    N

    N

    N

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    OO O   @C3Lha%tLei6ure void#""0;0000

    O O O O O O O O O O O O O O O O

    EEE   @C3Lha%tLei6ure void#""0A0000

    E E E E E E E E E E E E E E E

    !!!   @C3Lha%tLei6ure void#"""0000

    !

    !

    !

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    Fuel Clad Tem& in Central and Hot ChanneFuel Clad Tem& in Central and Hot Channe

    FC 9loc0a%e !9D9A" Sa/le Results

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        G   r   u   p   p   o    R

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       a   r   e    S .

        P    i   e   r   o

       a

        G   r   u   p   p   o    R

        i   c   e   r   c   a    N   u   c    l   e

       a   r   e    S .

        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

    FC 9loc0a%e !9D9A" - Sa/le Results

    Hot channel ," :W- total !loca'e in 02 s

    $o scram si'nal actuated

    /e&ere *uel Assembly damage

    : .1; .;: .*; .:: .1; .;: .*; 1.:: 1.1; 1.;:

    2ime (s+

    -;.:

    :

    ;.:

    :.:

    ;.:

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    1;.:

    7:.:

    7;.:

       %  a  s  s   F   l  o  <    3

      a   t  e   (   =  g   /  s   +

    JinGra% ;' / 0/"/"00A

    KKK CFA"8CBLOCHAGE $%lo*.""00000

    K K K K K K K K K K K K K K K K K K K K

    Fuel Clad Tem& in 6loced ChannelFuel Clad Tem& in 6loced Channel

    6loced Channel Po.er6loced Channel Po.er

    6loced Channel :ass Flo.6loced Channel :ass Flo.

    Conclusions

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        P    i   e   r   o

       a

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       a   r   e    S .

        P    i   e   r   o

       a

        G   r   a    d   o

        G   r   a    d   o

    Conclusions /R$SP/41$IPI deelo&ed or Ar'entinean electric utilit( $ASA so&histicated

    RELAP7"# models or Atucha II $PP

    "# $% TH )280 channel nodaliation+ .as &resented

    "# $% TH model setu& re>uired stron' interactions .ith other technolo'(=elds ,e'5 CF#5 neutron DSecs 'eneration-

    RELAP7"# models calculations .ill constitute the Cha&ter ;7 o the FSAR orthe Atucha II licensin'

    RELAP7"# demonstrated to !e a er( so&histicated tool5 allo.in' a detailed

    modellin' o all releant &henomena B &eculiarities o the Atucha II desi'n %e( &oints or the code im&roement .ere identi=ed and su''ested to I$L

    E'?

    Increase o the allo.a!le Tri& cards

    Increase the num!er o "# @olumes &er :ulti# com&onent

    Online Cross Section li!raries inter&olation

    Automatic Calculation o Reactiit( com&onents ,e'5 #o&&ler reactiit(5 coolanttem& reactiit(5-

    Further .ors are on'oin' at /R$SP/41$IPI in order to?

    Com&lete models >uali=cation

    Etend the model to a ull RP@ "# TH re&resentation5 includin' the simulation o all