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Atomerőművi reaktor töltettervezése, fűtőelem átrakás, reaktorfizikai korlátok, indítási mérések. Nemes Imre, Beliczai Botond PA Zrt. Tartalom. Üzemanyag cseréről általában Reaktorfizikai korlátok Reaktorfizikai mérések és értékelésük Töltettervezés módszerei és eszközei Pakson. - PowerPoint PPT Presentation
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Atomerőművi reaktor töltettervezése, fűtőelem
átrakás, reaktorfizikai korlátok, indítási mérések
Nemes Imre, Beliczai BotondPA Zrt
Tartalom
• Üzemanyag cseréről általában• Reaktorfizikai korlátok• Reaktorfizikai mérések és
értékelésük• Töltettervezés módszerei és
eszközei Pakson
Üzemanyag csere általában
• Ciklikus működésű reaktorok : PWR,BWR• 1 ciklus (kampány) hosszát
meghatározzák – technológia feltételek, gazdaságossági
megfontolások– reaktivitás tartalék
• Reaktivitás tartalék : – friss üzemanyag értékessége : dúsítás,
uránsúly, geometria– átlagos kiégés
Dúsítás-kiégés-kampányhossz
Tipikus VVER-440 töltet
1
319.03
2
213.55
3
321.18
4
213.52
5
212.81
6
211.75
7
326.71
8
10.000
9
10.000
10
323.45
11
212.84
12
323.81
13
213.99
14
324.90
15
210.70
16
324.61
17
323.22
18
10.000
19
436.51
20
214.00
21
323.37
22
210.73
23
317.76
24
322.89
25
10.000
26
10.000
27
435.43
28
214.07
29
323.44
30
213.55
31
211.77
32
325.60
33
10.000
34
10.000
35
214.07
36
323.11
37
28.462
38
10.000
39
433.65
40
10.000
41
435.61
42
28.502
43
321.27
44
325.91
45
433.42
46
434.62
47
435.35
48
323.45
49
10.000
50
10.000
51
10.000
52
434.67
53
324.95
54
10.000
55
10.000
56
435.67
57
10.000
58
435.04
59
436.99
Time= 0.00 eff.day
Power= 1375.000 MW
Tin.= 266.500 C
Mod.Flow= 30450.0 t/h
Cb= 6.655 g/kg
Reactivity= 0.0001 %
h6 pos.= 200.000 cm
2 -Ass.pos.
3 -AssAge 23.8 -AssBu[MWd/kgU]
AssAge:
3.84: 4.04
3.63: 3.84
3.43: 3.63
3.23: 3.43
3.02: 3.23
2.82: 3.02
2.62: 2.82
2.41: 2.62
2.21: 2.41
2.01: 2.21
1.80: 2.01
1.60: 1.80
1.40: 1.60
1.19: 1.40
0.99: 1.19
Results of C-PORCA Calculations
Unit=3 Cycle=16
code info:/3/16/val/kov/0/-/-
parameters: value: sec: ass.pos: pinpos: layer:
Ass.Pow-max[MW]: 5.310 1 49
Ass.Bu-max[MWd/kgU]: 36.99 1 59
PinPow-max[kW]: 45.58 1 50 1
PinBu-max[MWd/kgU]: 41.86 1 59 120
Tsub-max[C]: 315.6 1 38 83
Nlin-max[W/cm]: 247.8 1 50 1 9
Nlin-limit[W/cm]: 325.0 1 50 1 9
LocPinBu-max[MWd/kgU]: 48.52 1 59 120 8
Reaktorfizikai korlátok
• Neutron és hőfizikai paraméterek listája, amelyek a reaktor stacioner állapotát jellemzik
• Korlátként, keretként szolgálnak, betartásuk szükséges a reaktor biztonságos állapotához
• Tervezéskor olyan töltetet rakunk össze, hogy ezek a limitek teljesüljenek
The way of determination during SA
• Equilibrium cycle features used as a basis• Key parameters of a given analysis were chosen• Parameters adjusted to provide conservative
results
• Conservatism include : – Uncertainty of parameter– Deviations in transient cycles
• Conservatism limited by – acceptance criteria– physical feature of model
SABL tables/1Local power and temperature limits
Burnup limits
Parameter Limitation Reactor state
Maximal linear heat rate () < 325 W/cm(burnupdependent)
all
Maximal subchanel outlet temperature Tsat all
Parameter Limitation
Assembly burnup < 49 GWd/tUPin burnup < 55 GWd/tUPin local (pellet) burnup < 64 GWd/tU
SABL tables/2Limits of control rod worth
Limits on reactivity conditions
Parameter Limitation Reactor state
Efficiency of all control rods, except the most effective one > 5100 pcm all
Integral efficiency of group 6 rods (regulating group ) > 1300 pcm< 2500 pcm
all
Efficiency of one ejected rod < 210 pcm< 730 pcm
FPHZP
Differential rod efficiency < 0.037 $/cm near critical
Parameter Limitation Reactor state
Critical boric acid concentration < 10.5 g/kg all (HZP)Shutdown margin (1) <-2000 pcm HZP ( 260 C)Shutdown margin (2) < 0 ZP, 210 CMinimal subcriticality during refuelling condition (themost effective follower in the core)
< -5000 pcm Zero power , 100 C
SABL tables/3
Reactivity feedback coefficient limits
Parameter Limitation Reactor state
Boric acid efficiency < -1900 pcmkg/g> -1000 pcmkg/g
allall
Moderator temperature efficiency < 0.0 pcm/K> -70.0 pcm/K all
Doppler efficiency < -2.4 pcm/K> -4.9 pcm/K
all
Uncertainty determination
• linear power, subchanel temperature burnup limits : a detailed analysis taking into account material tolerances and calculation errors
• boron concentration, boron worth, moderator temperature coefficient, control rod worth : deviations between the measured and calculated parameter values.
• Rest of parameters : benchmark calculations
Parameter uncertaintiesParameter Uncertainty
Maximal linear heat rate 39 W/cmMaximal subchanel outlet temperature 7.5 C
Assembly burnup 7.65 %Pin burnup 13.6 %Pin local (pellet) burnup 13.6 %
Efficiency of all control rods, except the most effective one 10 %Integral efficiency of group 6 rods (regulating group ) 10 %Efficiency of one ejected rod 10 %Differential rod efficiency 0.00462 $/cm
Critical boric acid concentration 4.5 %Shutdown margin (1) 750 pcmShutdown margin (2) 750 pcmMinimal subcriticality during refuelling condition (the most effectivefollower in the core)
750 pcm
Boric acid efficiency 100 pcm/kg*gModerator temperature efficiency 2.5 pcm/CDoppler efficiency 20 %
Startup test at NPP Paks
What we measure ?
Why we measure these ?
How to evaluate results ?
How we declare the acceptance of results ?
Purposes of measurements
Long term : data collection f or the testing ofcalculated parameter uncertaintyShort term : immediate decision to declare the“goodness” of refuelled core
checking of parameter value diff erence between measured and calculated
value
Both case purpose : check the most importantparameters summarised in SABL table
Test Short description
Criticality test Criticality at 210-220 CMeasur. of critical cb af terstabilisation
Test of control roddriver connection
Reactivity changes during themovement of each CR
/ t measurement Heating of primary circuit 210-260 CMeasurement of reactivitythrough quasistatic states
Effi ciency of centralrod
Measurement of reactivitythrough quasistatic states
Measurement ofeff ectivityof all rods except themosteff ective one
Rod drop measurement( dynamic)
Thermocouplecalibration
I n a stable state withhomogeneous temperatures
/ h6, / cb
measurement
Dilution of primary circuitMeasurement of reactivitythrough quasistatic states
SymmetrymeasurementCheck of powerdistribution
on power
Start-up testprogramof NPP Paks
Types of acceptance criteria
Absolute :
prescription f or the measured value provide the parameter value within the limit
Relative :
prescription f or the bias f rom calculated provide the accuracy of calculation within a
range through the calculation and bias provide the
parameter values within the limit
Measuredparameters
AcceptancecriteriaAbsolute Relative
Critical boron atHZP
yes yes
/ tm yes yesEff ectivity of allrods except themost eff ective one
no yes
effi ciency ofcentral rod
no yes
/ h6, (h6) no yes
Measured parameters and acceptance criterias at NPP Paks practice
INPUT surface
(BEA )
General INPUT
Burnup state files
C-PORCA 6.0
OUTPUT surface
( C-COW )
General Output
HELIOS
CERBER
( BOSSY version )
VERONA Cycle data
Refuelling documentation FGCS library
FGCS library
COBRA COBRA
Töltettervezés módszerei és eszközei Pakson
HELIOS application for Paks
• Generate few-group cross section libraries for C-PORCA 2.0, 5.0, nodal and pin-wise models
• Validate few-group diffusion codes calculating different test cases
HELIOS few-group cross section calculations / Paks specific
features • 45 (190) -group 2D transport code• detailed and flexible geomery• developed handling and services
• few-group parameters for non-multiplying regions as well - no boundary conditions
• Pin-cells with different spectral position handled separately
Geometries for HELIOS calculation
CERBER - for refuelling design
• Fast and effective 3D nodal diffusion model ( C-PORCA 2.0)
• Interactive WINDOWS surface -Bossy version
• Different options of automatic optimisation
The BOSSY WINDOWS surface for CERBER calculations
C-PORCA 6.0
• 2-group 3D diffusion code - combined nodal and pin-wise calculations
• 20 axial layers, 127 cells/assembly• Modules included for data
preparations for VERONA system• Detailed and continuous validation • Developed services
Evaluation of C-PORCA results using C-COW output surface
C-PORCA 5.0 V&Vmathematical benchmarks
HELIOS tests : nodal and pinwise MCNP reference calculations NPP Paks measured data (more then 60
cycles) : global parameters, assembly power distribution
Validation benchmarks : xenon, power distributions, non-measured parameters and cases