eurotrans wp 1.5 meeting fzk – karlsruhe, november 27-28, 2008 fpn-fisnuc / bologna eurotrans –...

EUROTRANS WP 1.5 MeetingFZK – Karlsruhe, November 27-28, 2008

ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE


FPN-FISNUC / Bologna

EUROTRANS – DM1

EFIT Transients Analysis with RELAP5, SIMMER-III and

RELAP/PARCS Codes

G. Bandini, P. Meloni, M. Polidori

2



EUROTRANS WP 1.5 Meeting, Karlsruhe, November 27-28, 2008

SUMMARY

Analyzed Transients

Results from RELAP5 Calculations Steady-state Results

Protected Transients: PLOF, PLOH, and PLOF + PLOH

Results from SG Tube Rupture with SIMMER-III

Results from RELAP/PARCS Coupled Calculations (Presented by M. Polidori)

Spurious Beam Trips

Unprotected Transients: ULOF, ULOH, ULOF + ULOH, Beam Overpower

Conclusions

3




Analyzed Transients

Transient BU state Beam Trip CODE Transient time (s)

PLOF BOC After 3 s RELAP5 100

PLOH BOC Tlead out > 525 C RELAP5 5000

PLOF + PLOH BOC After 3 s RELAP5 5000

SG tube rupture - - SIMMER-III 30

Spurious beam trip BOC 1 s, 10 s (interval) RELAP/PARCS -

PROTECTED TRANSIENTS

Transient BU state Beam Power CODE

ULOF BOC 100% RELAP/PARCS

ULOH BOC 100% RELAP/PARCS

ULOF + ULOH BOC 100% RELAP/PARCS

Beam overpower BOC 120% at HFP RELAP/PARCS

UNPROTECTED TRANSIENTS

4




RELAP5 Model of EFIT

22

173

82

151

152153154

Pth

Branch

121

Pb side Bra

nch

07

Jun 23 Jun 83

01 - 0405

01

170

Pumps

113

Branch 176Branch 175 (177/8/9)

62

DHR

SGs

010102

112

water side

Annulus181

(182/3/4)

Pipe281

(282/3/4)

02

Branch 171

01

Jun 63

109

311

310

211

210

111

110

108

Active core

By-

pas

s &

Ref

lect

or

Ou

ter

Hot

Ou

ter

aver

age

Mid

dle

ave

rage

Inn

er a

vera

ge

Mid

dle

Hot

Inn

er H

ot TA

RG

ET

SGs

UPPER PLENUMBranch 120

LOWER PLENUMBranch 100

Branch 160

161

102

01

0807 06 05 03 02 01 0904

02 06 05 03 02 01 0804

09

Jun 114 Jun 104 Jun 106

Jun 105

22

173

82

151

152153154

Pth

Branch

121

Pb side Bra

nch

07

Jun 23 Jun 83

01 - 0405

01

170

Pumps

113

Branch 176Branch 175 (177/8/9)

62

DHR

SGs

010102

112

water side

Annulus181

(182/3/4)

Pipe281

(282/3/4)

02

Branch 171

01

Jun 63

109

311

310

211

210

111

110

108

Active core

By-

pas

s &

Ref

lect

or

Ou

ter

Hot

Ou

ter

aver

age

Mid

dle

ave

rage

Inn

er a

vera

ge

Mid

dle

Hot

Inn

er H

ot TA

RG

ET

SGs

UPPER PLENUMBranch 120

LOWER PLENUMBranch 100

Branch 160

161

102

01

0807 06 05 03 02 01 0904

02 06 05 03 02 01 0804

09

Jun 114 Jun 104 Jun 106

Jun 105

0.00

Steam Generator

DHR

Proton beam

Pump

RELAP5 Nodalization SchemeEFIT Reactor Block

5




Core Power Distribution

Axial power profile in average SA of different core zones

90

100

110

120

130

140

150

160

170

0.0 7.5 15.0 22.5 30.0 37.5 45.0 52.5 60.0 67.5 75.0 82.5 90.0

Z (cm)

Lin

ea

r p

ow

er

(W/c

m)

inner core (average SA)

middle core (average SA)

outer core (average SA)

110

120

130

140

150

160

170

180

190

200

0.0 7.5 15.0 22.5 30.0 37.5 45.0 52.5 60.0 67.5 75.0 82.5 90.0

Z (cm)

Lin

ear

po

we

r (W

/cm

)

inner core (hot SA)

middle core (hot SA)

outer core (hot SA)

Axial power profile in hot SAs

Axial power profile in average SAs

MCNP Calculations (ENEA)• Total reactor power = 396.2 MW

• Active core power = 375 MW• Inner = 94 MW• Middle = 140 MW• Outer = 141 MW

• Reflector power = 10 MW

• Target power = 11.2 MW

Radial power form factor(BOC)

6




RELAP5 Steady-State CalculationMaximum Core Temperatures (C) (BOC)

Parameter Inner core

Middle core

Outer core

Lead temperature (average pin of average SA) 482 482 482 Lead temperature (average pin of hot SA) 490 491 502 Lead temperature (hot pin of hot SA) 490 491 502 Clad temperature (average pin of average SA) 502 500 495 Clad temperature (average pin of hot SA) 513 510 517

Clad temperature (hot pin of hot SA) 516 511 519

Fuel temperature (average pin of average SA) 1129 1153 1052 Fuel temperature (average pin of hot SA) 1193 1237 1248 Fuel temperature (hot pin of hot SA) 1297 1280 1333

GAP behavior at BOC according to FZK-SIMADS detailed analysis (114 μm)

Good agreement with SIMADS results

Axial Temperature Profile, CZ3, BOC, Hot Pin of Hot SA

400

500

600

700

800

900

1000

1100

1200

1300

1400

-45 -35 -25 -15 -5 5 15 25 35 45

Axial core position (cm)

Te

mp

era

ture

s (

°C)

Tlead-3 h-hTclad-3 h-hTsurf-3 h-hTfuel-3 h-h

Axial temperature profile

Hot pin of hot SA of outer core zone

7




PLOF Transient Results

0.0

0.2

0.4

0.6

0.8

1.0

1.2

0 20 40 60 80 100Time (s)

P/P

o, Q

/Qo

Core power

Core flowrate

200

400

600

800

1000

1200

1400

0 20 40 60 80 100

Time (s)

Tem

pera

ture

(C

)

Core inlet

Max core lead

Max core clad

Max core fuel

300

350

400

450

500

550

600

0 20 40 60 80 100

Time (s)

Tem

pera

ture

(C

)

SG inlet

SG outlet

Reactor trip at 3 s

Core flowrate undershoot

Max clad temperature = 609 C

No significant fuel temperature increase

SG primary side temperatures

Core temperatures

Core power and flowrate

8




PLOH Transient Results (1)

200

400

600

800

1000

1200

1400

0 40 80 120 160 200

Time (s)

Tem

pera

ture

(C

)

Core inlet

Max core lead

Max core clad

Max core fuel

350

400

450

500

550

600

650

0 40 80 120 160 200

Time (s)

Te

mp

era

ture

(C

)Core inlet

Max core clad

Max core lead

Max core fuel

Reactor trip at 55 s (Tlead > 525 C)


Max fuel temperature = 1356 C

Core Temperatures

9




200

400

600

800

1000

1200

1400

0 1000 2000 3000 4000 5000

Time (s)

Tem

pera

ture

(C

)

Core inlet

Max core lead

Max core clad

Max core fuel

Max vessel wall


Max vessel temperature is below the safety limit of 450 C

Core and Vessel Temperatures

370

390

410

430

450

470

490

510

0 1000 2000 3000 4000 5000

Time (s)

Tem

pera

ture

(C

)

Core inlet

Max core lead

Max core clad

Max core fuel

Max vessel wall

10





0

5

10

15

20

25

30

0 1000 2000 3000 4000 5000

Time (s)

Pow

er (

MW

)

Core power

DHR power

380

400

420

440

460

480

0 1000 2000 3000 4000 5000

Time (s)

Tem

pera

ture

(C

)

DHR inlet

DHR outlet

DHR system (3 units) reaches full operation (20 MW) after about 500 s

Temperature reduces in the medium term and stabilizes below 440 C

0.0

0.2

0.4

0.6

0.8

1.0

1.2

0 1000 2000 3000 4000 5000

Time (s)

P/P

o, Q

/Qo

Core power

Core flowrate

DHR Temperatures


Core and DHR Powers

11




PLOF + PLOH Transient Results (1)

200

400

600

800

1000

1200

1400

0 40 80 120 160 200

Time (s)

Tem

pera

ture

(C

)

Core inlet

Max core lead

Max core clad

Max core fuel

350

400

450

500

550

600

650

0 40 80 120 160 200

Time (s)

Tem

pera

ture

(C

)Core inlet

Max core lead

Max core clad

Max core fuel

Reactor trip at 3 s


No significant fuel temperature increase

Core Temperatures

12





200

400

600

800

1000

1200

1400

0 1000 2000 3000 4000 5000

Time (s)

Tem

pera

ture

(C

)

Core inlet

Max core lead

Max core clad

Max core fuel

Max vessel wall

390

410

430

450

470

490

510

530

550

0 1000 2000 3000 4000 5000

Time (s)

Tem

pera

ture

(C

)

Core inlet

Max core lead

Max core clad

Max core fuel

Max vessel wall

Max vessel temperature is below the safety limit of 450 C

Core and Vessel Temperatures

13





0.0

0.2

0.4

0.6

0.8

1.0

1.2

0 1000 2000 3000 4000 5000

Time (s)

P/P

o, Q

/Qo

Core power

Core flowrate

0.0

0.2

0.4

0.6

0.8

1.0

1.2

0 20 40 60 80 100

Time (s)

P/P

o, Q

/Qo

Core power

Core flowrate



0

5

10

15

20

25

30

0 1000 2000 3000 4000 5000

Time (s)

Pow

er (

MW

)

Core power

DHR power

380

400

420

440

460

480

0 1000 2000 3000 4000 5000

Time (s)

Tem

pera

ture

(C

)

DHR inlet

DHR outlet

Core and DHR Powers

DHR Temperatures

14




SGTR: SIMMER-III Analysis

R

Z

Core

Steamgenerator

Simplified R-Z Geometry (29 x 41)

R

Z

Core

Steamgenerator

Simplified R-Z Geometry (29 x 41)

SIMMER-III Model of EFIT

Preliminary Design

SCENARIO:

1 and 5 tubes ruptureat SG bottom

15




SGTR: SIMMER-III Results

EFIT ReactorSGTR Accident

Material Fractions

5 Tubes RuptureTime = 0 – 30 s

0.1 s 1 s

3 s 10 s 30 s

EFIT ReactorSGTR Accident

Material Fractions

5 Tubes RuptureTime = 0 – 30 s

0.1 s 1 s

3 s 10 s 30 s

16




SGTR: SIMMER-III Results

0

1

2

3

4

5

6

7

8

0 5 10 15 20 25 30Time (s)

Ma

ss F

low

rate

(k

g/s

) 1 Tube

5 Tubes s

0.0E+00

2.0E+06

4.0E+06

6.0E+06

8.0E+06

1.0E+07

1.2E+07

1.4E+07

1.6E+07

0 5 10 15 20 25 30Time (s)

Pre

ssu

re (

Pa)

1 Tube

5 Tubes

0

100000

200000

300000

400000

500000

600000

0 5 10 15 20 25 30Time (s)

Pre

ssu

re (

Pa)

1 Tube

5 Tubes

Break mass flowrate

Cover gas pressure

SG secondary side pressure

SG primary side pressure (5 tubes)Pressure (Pa)Pressure (Pa)

17




CONCLUSIONS

Steady-state RELAP5 calculations show that in normal operation at nominal power the maximum core temperatures (lead, clad and fuel) are well within safety limits

Results from protected transient analysis with RELAP5 show that the maximum core and vessel temperatures remains below safety limits in the short and long term even in the unfavorable cases of total loss of forced circulation in the primary system and total loss of heat removal by the secondary system

Investigation of SGTR accident with SIMMER-III gives indication of: (1) no concern for cover gas pressure increase limitation by protective measures, (2) no concern for steam recirculation at core inlet with void reactivity effect, (3) pressure peaks and their mechanical effect on SG surrounding structure need more detailed analysis

eurotrans wp 1.5 meeting fzk – karlsruhe, november 27-28, 2008 fpn-fisnuc / bologna eurotrans –...

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