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INSTITUT für NEUTRONENPHYSIK und REAKTORTECHNIK (INR)

Application of MELCOR 1.8.2 (fusion version) and MELCOR 2.1 on the DEMO Helium

Cooled Pebble Bed blanket concept.

Bruno Gonfiotti

PhD student at University of Pisa

Dipartimento di Ingegneria Civile ed Industriale (DICI)

Email: bruno.gonfiotti@for.unipi.it

(2)

Outline

1. Introduction - Motivation.

2. Description of DEMO/HCPB and its PHTS.

3. PHTS modellization for Stationary runs.

4. PHTS modellization for In-Vessel LOCA scenarios.

5. Conclusions.

6. Acknowledgments.

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Introduction - Motivation

Several incidental/accidental conditions can hamper the safety of a fusion reactor, and the Loss of Coolant Accident (LOCA) of the blanket Primary Heat Transfer System (PHTS) is one of the most challenging [1].

To date, one of the main codes employed for incidental conditions analyses in fusion installations is MELCOR 1.8.x. Although, this version is quite old, and newer version were released (MELCOR 2.1.6342).

The aim of this work is to stress the positive and negative aspects of M 1.8.2

and M 2.1 through a “version-to-version” comparison employing the same

nodalisation.

(4)

DEMO represents the prosecution of the scientific and technological challenge of ITER, and it should

demonstrate the suitability of the fusion power as a sustainable energy power source.

To date, several different DEMO concepts exist basing on the various “blanket concept” proposed:

HCPB – Helium Cooled Pebble Bed

WCLL – Water Cooled Lithium Lead

DEMO & HCPB blanket concept (1/3)

(5)

DEMO & HCPB blanket concept (2/3)

DEMO is a tokamak machine as ITER;

(6)

DEMO & HCPB blanket concept (3/3)

3 (48) OB segments 2 (32) IB segments 16 sectors

Blanket 6 box rows

(7)

PHTS description: Reference design

Two independent coolant loops for the Out-Board (OB) segments and two for the In-Board (IB) ones. [2]

He as coolant at 8.0 MPa in the temperature range of 300 – 500

° C. He inventory ~7000 kg each OB coolant loop. [3]

Each OB loop removes 910.5 MW. [3]

6 Cooling trains (CTs) with one helicoidal steam generator each (5 operational

and 1 spare). [2]

(8)

PHTS modellization: stationary run

13 CV (12–PHTS, 1-EV).

12 Flow Junction (FJs).

2 HSs (blanket and SG).

Characteristics MELCOR

EV Temperature [K] 313.35

Blanket temp. [K] 773.15

SG temp. [K] 573.15

Total pressure drop [MPa] 0.37 Heat flow [W/m

2

] 60700.0

Characteristics MELCOR

EV Volume [m

3

] 70000.0 Heat transfer area [m

2

] 15000.0 Blanket HS temp. [K] 773.15

SG HS temp. [K] 573.15

Total mass flow [kg/s] 875.5

(9)

Stationary run results (1/2)

Parameter Reference 1.8.2 2.1 Difference [%]

Blanket Total Pressure [MPa] - 8.19 8.2 0.1 %

SG Total pressure [MPa] - 7.82 7.83 0.1 %

Pressure drops [MPa] 0.37 0.37 0.37 0.0 %

Mass Flow rate [kg/s] 875.5 872.8 872.3 < 0.04 %

He mass [kg] ~ 6620.0 6795.4 6795.4 3.0 %

Blanket CV Temp. [K] 773.15 771.39 773.39 ~ 0.2 %

Blanket HS Temp. [K] 773.15 773.43 781.61 < 1.1 %

SG CV Temp. [K] 573.15 573.83 573.82 ~ 0.1 %

SG HS Temp. [K] 573.15 570.3 570.52 < 0.5 %

HTC Blanket [W/m

2

K]

-

29686.8 7384.7 75.0 %

HTC SG [W/m

2

K]

-

17221.8 18421.1 7.0 %

The results of the stationary run are quite similar, but great differences exist on

the inner heat transfer coefficients of the two HSs.

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Stationary run results (2/2)

Differences on the HTC Due to the different temperature equilibrium among CV and HS.

No differences changing the default SC from 2.1 to 1.86.

One difference exists: CPFPL and CPFAL (critical pool fractions) values.

In 1.8.2 set both to 0.0;

In 2.1 set >0.0 due to numerical error if set to 0.0

Although, the stationary runs provide exhaustive results. Further analyses with complex nodalisations are required.

) (

'' HTC T

HS

T

CV

q = −

M 1.8.2 To remove 60700.0 W/m

2

with a ∆ T of 2.04 K an HTC of 29754.9 W/m

2

K is needed.

M 2.1 To remove 60700.0 W/m

2

with a ∆ T of 8.22 K

an HTC of 7384.7 W/m

2

K is needed.

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In-Vessel LOCA: Approach

Helium release inside the Vacuum Vessel (VV), and opening of a rupture disk connecting the VV and the Expansion Volume (EV) once reached the imposed set-point.

Parametric study

Different rupture area

0.12 m

2

(max) 1.0E-3 m

2

1.0E-5 m

2

D

C

B

A

(12)

In-Vessel LOCA: modellisation

Parameter MELCOR

EV Volume [m

3

] 70000.0

EV temp. [K] 313.35

VV Pressure [Pa] 210.0 VV Volume [m

3

] 1860.0 VV internal Temp. [K] 473.15 W dust mass [kg] 10.0

T mass [kg] 0.2

R. D. area [m

2

] 1.0 R. D. set point [MPa] 0.15

PHTS as in stationary run.

VV as a single volume.

Rupture Valve connecting PHTS and VV.

Rupture disk connecting VV and EV.

(13)

In-Vessel LOCA: 0.12 m

2

(1/7)

Similar PHTS depressurization, but numerical instabilities in M 2.1.

Similar EV depressurization.

VV depressurization rate different, especially from 114.0 s to 135.0 s.

The helium ingress inside the VV could cause the W dust mobilisation.

0.00 0.25 0.50 0.75

90.0 105.0 120.0 135.0 150.0 165.0

Total pressure[MPa]

Time [s]

PHTS 1.8.2 EV 1.8.2 VV 1.8.2

PHTS 2.1 EV 2.1 VV 2.1

(14)

In-Vessel LOCA: 0.12 m

2

(2/7)

0.0 120.0 240.0 360.0 480.0 600.0

95.0 105.0 115.0 125.0 135.0 145.0 155.0 165.0

Mass Flow Rate [kg/s]

Time [s]

Rupture 1.8.2 Disk 1.8.2 Rupture 2.1 Disk 2.1

The different depressurization rate of the VV is due to a slightly

different prediction of the mass

flow rates across the rupture disk.

(15)

In-Vessel LOCA: 0.12 m

2

(3/7)

450.0 500.0 550.0 600.0 650.0 700.0 750.0 800.0 850.0

90.0 140.0 190.0 240.0 290.0

Temperature [K]

Time [s]

BL 1.8.2 SG 1.8.2 BL 2.1 SG 2.1

Two phenomena influence

the temperature trends.

Helium expansion

Unbalanced blanket-SG power.

Blanket M 2.1 temperature decrease when the VV and EV reach the same pressure.

SG Same trend, but

different temperature

decrease magnitude (~25 K).

(16)

In-Vessel LOCA: 0.12 m

2

(4/7)

450.0 550.0 650.0 750.0 850.0 950.0 1'050.0 1'150.0 1'250.0 1'350.0

90.0 190.0 290.0 390.0 490.0

Temperature [K]

Time [s]

VV 2.1 VV 1.8.2

Max VV temperature:

1255 K – M 2.1 1050 K – M 1.8.2 Different temperature trends after 110.0 s

150.0 s M2.1 <15 K 330.0 s M2.1 >12 K No apparent causes for this behaviour (max.

pressurization identical).

(17)

0.0 5.0 10.0 15.0 20.0 25.0 30.0

0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 1.0

Percentage [%]

Dust size [µm]

In-Vessel LOCA: 0.12 m

2

(5/7)

The fast pressurization of the VV can lead to the W dust resuspension.

W dust data taken from STARDUST experiment [4].

M lacks of a resuspension model.

Two cases investigate:

W injected 1 s before the rupture event.

W injected during the

rupture event.

(18)

In-Vessel LOCA: 0.12 m

2

(6/7)

M 1.8.2. Injected mass overestimated (~200g).

M 1.8.2 W mass mainly deposited on VV.

M2.1 W mass mainly in EV atmosphere.

M 2.1 results similar to ASTEC ones.

Further investigation needed.

0.0 2.0 4.0 6.0 8.0 10.0 12.0

95.0 100.0 105.0 110.0 115.0

Tungsten Mass [kg]

Time [s]

VV atm 1.8.2 EV atm 1.8.2 VV dep 1.8.2 EV dep 1.8.2 VV atm 2.1 EV atm 2.1 VV dep 2.1 EV dep 2.1

(19)

Conclusions

Version-to-version comparison among M 1.8.2 (fusion version) and M 2.1.6342 employing the same nodalisation.

Stationary run: Different blanket HTC value, but reliable and satisfactory results for both versions.

In-Vessel run: Minor differences, except for the atmospheric temperatures and the W dust behaviour.

In the future the introduction of fusion specific models of the

1.8.6 version inside the 2.1 version could be an interesting

evolution.

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Acknowledgments

The work with MELCOR 1.8.2 has been performed at Karlsruhe Institute of Technology (KIT) at Karlsruhe (D).

The work with MELCOR 2.1 has been performed at

University of Pisa (UNIPI) at Pisa (I).

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Thank you for your attention

Bruno Gonfiotti

PhD student at University of Pisa

Email: bruno.gonfiotti@for.unipi.it

Thank you for your attention

Bruno Gonfiotti

PhD student at University of Pisa

Email: bruno.gonfiotti@for.unipi.it

(22)

References

1. D. N. Dongiovanni, T. Pinna, and D. Carloni, “RAMI Analysis for DEMO HCPB blanket concept cooling system”, Proceedings of Symposium of Fusion Technology 2014 (SOFT2014), San Sebastian, Spain, September 29-October 3, 2014.

2. M. D. Donne, "Conceptual Design of the Cooling System for a DEMO Fusion Reactor with Helium Cooled Solid Breeder Blanket and Calculation of the Transient Temperature Behavior in Accidents," Karlsruhe, 1992.

3. D. Carloni and S. Kecskes, "Helium Cooled Blanket Design Development," Karlsruhe, 2012.

4. M. T. Porfiri, N. Forgione, S. Paci and A. Rufoloni, "Dust mobilization experiments in

the context of the fusion plants - STARDUST facility," in Seventh International

Symposium on Fusion Nuclear Technology - ISFNT-7 Part B, 2006.

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