Transcript Diapositiva 1

FRAPCON/FRAPTRAN USERS GROUP MEETING
CIEMAT ACTIVITIES
on
FRAPCON/FRAPTRAN APPLICATIONS
(2012-2013)
Unit of Nuclear Safety Research
Division of Nuclear Fission
CIEMAT-Madrid
Spain
Nuclear Safety Research Unit
Charlotte , NC (USA), 19.09.13
FRAPCON/FRAPTRAN USERS GROUP MEETING
MAIN ACTIVITIES
FRAPTRAN-1.4
FRAPCON-3.4
Extension to DS
Steady State UA
(FRAPCON-3.4xt) (Impact on RIA modeling)
AICAST (ENRESA)
Nuclear Safety Research Unit
Ramps
(SCIP)
RIA
(OECD)
LOCA
(HALDEN)
TERMOMEC (CSN)
Charlotte , NC (USA), 19.09.13
FRAPCON/FRAPTRAN USERS GROUP MEETING
MAIN ACTIVITIES
DS
- FRAPCON-3.4xt application to predict cladding mechanical performance based
on CFD calculations
UA
- Impact of steady state uncertainties (FRAPCON) on RIA modeling calculations
(SCANAIR)
Ramps - FRAPTRAN capability to model power ramps from 3rd SCIP Benchmark
- Comparison with FRAPCON results applied to similar ramps from 2nd SCIP
Benchmark
RIA
LOCA
- RIA fuel code Benchmark calculations (FRAPTRAN vs SCANAIR)
- FRAPTRAN capability to model HALDEN tests: IFA-650.xx
Nuclear Safety Research Unit
Charlotte , NC (USA), 19.09.13
FRAPCON/FRAPTRAN USERS GROUP MEETING
THANK YOU FOR YOUR ATTENTION
Nuclear Safety Research Unit
Charlotte , NC (USA), 19.09.13
FRAPCON/FRAPTRAN USERS GROUP MEETING
FRAPCON-3.4xt application to predict cladding mechanical performance
based on CFD calculations
10000
Cask blockage
Relative increment (%)
Creep
1000
Dissolved H
100
10
1
0.1
0.01
0.001
0.0001
40-25
40-45
60-25
60-45
Burnup (GWd/tU)-Storage time (years)
F. Feria, J. Penalva, L.E. Herranz, “Thermo-mechanical analysis of cladding behaviour under cask blockage
conditions”, Top Fuel 2013
Nuclear Safety Research Unit
Charlotte , NC (USA), 19.09.13
FRAPCON/FRAPTRAN USERS GROUP MEETING
Impact of steady state uncertainties on RIA modeling calculations
I. Sagrado, L.E. Herranz, “Impact of steady state uncertainties on RIA modeling calculations”, Top Fuel 2013
Nuclear Safety Research Unit
Charlotte , NC (USA), 19.09.13
FRAPCON/FRAPTRAN USERS GROUP MEETING
FRAPTRAN capability to model power ramps from 3rd SCIP Benchmark
xM1 Ramp
348
346
344
342
340
338
336
334
332
330
328
326
-0.95 %
T clad outer (ºC)
325
FRAPTRAN (Conditioning end)
FRAPTRAN (Begin of ramp)
FRAPTRAN (End of ramp)
STUDSVIK data final ramp step t=8 min.
315
6%
310
305
300
FRAPTRAN (Conditioning end)
FRAPTRAN (Begin of final ramp step)
FRAPTRAN (End of final ramp step)
STUDSVIK data final ramp step t=26.5 h
295
285
50
0
100 150 200 250 300 350 400 450 500
Axial distance (m)
xM2 Ramp
3000
50
2700
0.9
2400
0.8
2100
40
1800
30
1500
1200
20
900
Peak PPN (Output code)
LHR (Studsvik data)
Clad Elongation (Output code)
Clad Elongation (EXP. DATA)
10
600
300
0
0
-4
-2
0
2
4
6
8
10
12
Time after RTL(min)
14
16
18
20
50
100
150 200 250 300
Axial elevation (m)
350
400
450
GE-1, POST-RAMP RESULTS
1
Av. Measur.
FRAPTRAN-1.4
0.7
DDpost (%)
60
Axial Power (kW/m )
320
290
0
Strains:
GE-1 Ramp (IFA-695.2)
330
Elongation (microns)
T clad outer (ºC)
Clad temperatures:
0.6
0.5
0.4
0.3
0.2
0.1
0
0
50
100
150
200
250
300
350
400
450
Axial distance (mm)
I. Vallejo, L.E. Herranz, “Simulations of four Ramp Tests from SCIP Project with FRAPCON-3.4/FRAPTRAN1.4
Codes”, DFN/SN-xx/OP-13 Technical Report (In Progress)
Nuclear Safety Research Unit
Charlotte , NC (USA), 19.09.13
FRAPCON/FRAPTRAN USERS GROUP MEETING
RIA fuel code Benchmark calculations (FRAPTRAN vs SCANAIR)
1200
1100
1.2
FRAPTRAN-1.4
SCANAIR-7.1
1.0
900
Clad hoop strain (%)
Fuel center temperature (C)
1000
FRAPTRAN-1.4
SCANAIR-7.1
800
700
600
500
0.8
0.6
0.4
400
0.2
300
200
0.060 0.062 0.064 0.066 0.068 0.070 0.072 0.074 0.076 0.078 0.080 0.082 0.084
Time (s)
0.0
0.060 0.062 0.064 0.066 0.068 0.070 0.072 0.074 0.076 0.078 0.080 0.082 0.084
Time (s)
I. Sagrado, I. Vallejo, L.E. Herranz, “Analysis of Experimental RIA Scenarios: CIEMAT Contribution to the
OECD RIA International Benchmark”, DFN/SN-02/OP-13. CIEMAT Technical Report
Nuclear Safety Research Unit
Charlotte , NC (USA), 19.09.13
FRAPCON/FRAPTRAN USERS GROUP MEETING
FRAPTRAN capability to model HALDEN tests: IFA-650.xx
1200
90
150
0
-100
50
END FRAPT SIMUL
450
300
70
60
BLOWDOWN
Clad Temp. (ºC)
Diff time failure pred-exp
900
0
100
200
300
400
40
30
20
10
Rod Pressure (bar)
80
1050
750
600
TCC1
TCC2
TCC3
FRAP BOTTOM
FRAP TOP
FRAP PPN (fail)
TCH1 Heater Temp lower
TCH2 Heater Temp middle
PF1
FRAP Press
IFA-650.10 Test
0
500
600
SECONDS (LOCA at t=0)
I. Vallejo, L.E. Herranz, “Modelización Post-Test del Experimento HALDEN IFA-650.10 con los Códigos de la
serie FRAP”, SNE, 2013
Nuclear Safety Research Unit
Charlotte , NC (USA), 19.09.13