IAEA Technical Meeting on IFMIF, Karlsruhe, 4-6 October 2005

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IAEA Technical Meeting on IFMIF, Karlsruhe, 4-6 October 2005

IFMIF neutronics and activation analyses:Li target, High Flux Test Module and Test

CellS.P. Simakov, U.Fischer, V. Heinzel

Association FZK-Euratom, Forschungszentrum Karlsruhe

F. Wasastjerna a) , P.P.H. Wilson b)

a) Association Euroatom-Tekes, Helsinki, Finland b) Fusion Technology Institute, University of Wisconsin, Madison, USA

Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft

2IAEA Technical Meeting on IFMIF, Karlsruhe, 4-6 October 2005

Computational Tools and Nuclear Data Base IFMIF neutron source simulation, neutron transport and nuclear responses calculations:

- McDeLicious code - for the neutron source simulation (using d-Li evaluated cross sections, updated by P.Pereslavtsev) and neutron transport- neutron cross sections from INPE/FZK-50, LA-150 general

libraries – for transport and nuclear responses

Radioactive inventory calculations:– deuteron induced inventories in the Li loop - by McDeLicious code

using evaluated Li(d,x)3H and Li(d,x)7Be cross sections files- neutron induced inventories in the IFMIF components by ALARA

inventory code with IEAF-2001 activation data library (up to 150 MeV)

IFMIF test cell model (F.Wasastjerna):– detailed 3d geometry model describing all principal sub systems of

the IFMIF test cell (d-beam tubes, Li-loop and target, test modules, test cell walls)


D-Li Neutron yields: Validation vs. thick target experiment

Experiment set-up with

pin d-beam and point n-detector:Neutron Spectra at well defined angles:

Peak at energy 15 MeV is clearly visible in well fine angle geometry.This peak is reproduced by 2005 updated d-Li evaluation within 10%

Li-target

d-beam

n-detector

= 1o

0 10 20 30 40 50 600.0

0.5

1.0

1.5

2.0

2.5

3.0

Baba et al.

Mann et al.

Experiment:

(60o)

(20o)

(2005 updated d-Li data)

MCNPX

MCDeLicious

Ed = 40 MeV, 0o

Neu

tron

Yie

ld,

1010

n/s

r/M

eV/

C

Neutron Energy, MeV

15%


Does IFMIF neutron spectra have 14 MeV peak ?

IFMIF fragment:

Neutron Spectra at Atom point

Angular smearing and multiple scattering smooth a 14 MeV neutron peak in HFTM,resulting to the shape without local extremes

d-beam

Li-jet

HFTM-rigs

CFTM-rods

= +/-10o

0 10 20 30 40 500.0

0.5

1.0Sum

High Flux Module

Scattering

Source

IFMIF: Ed= 40 MeV, I

d= 250 mA

Neu

tron

Spe

ctru

m,

1013

n/cm

2 /MeV

Neutron Energy, MeV

0.0

0.5

1.0

1.5

Sum

Scattering

Source

Creep Fatique Module

ITER(1.2Mw/m2)/10


Transport cross sections and nuclear responses

Responses in HFTM/IFMIF vs. Libraries(uncertainties due to XS data)

Evaluated neutron cross sections(LANL – solid, INPE/FZK – dash)

Parameter LANL INPE Differ. dpa-rate, 1/fpy 31.1 33.6 8 %

Heating, W/cm3 16.9 19.7 16 % H-production, appm/fpy 1602 1767 10 % He-production, appm/fpy 345 396 13 %

n-flux, 1014/cm2/s 7.05 7.43 5 % -flux, 1014 /cm2/s 3.38 3.59 6 %

1E-3 0.01 0.1 1 10 10010-4

10-3

10-2

10-1

100

101

102

103

104

105

56Fe

(n,dpa)

(n,)

(n,x)

(n,x) (n,xp)

Neutron Flux in HFTM

(n,tot)

[

b],

F

lux

[1011

/MeV

/cm

2 /s]

Energy, MeV

Expected uncertainties of IFMIF nuclear responses due to the transport cross sections data - (5- 15)%


3-dimensional nuclear responses in HFTM (40MeV@250mA)

HFTM Matrix & Nuclear Responses(averaged over the rig volume)

HFTM equatorial plane view

d-beam

Li - jet

HFTM (rig matrix)

UTM W plate

Eurofer (EF) content (and material density [g/cm3]) EF-39% (3.53) EF-87% (6.77) EF-52% (4.39) EF-39% (3.53) EF-87% (6.77) EF-52% (4.39) EF-39% (3.53) EF-87% (6.77) EF-52% (4.39) EF-39% (3.53) EF-87% (6.77) EF-52% (4.39)

Displacements per Fe atom [dpa/fpy]

16.4 19.9 19.7 16.3 22.3 26.2 25.5 22.1 31.3 35.0 34.9 31.3

H production per Fe atom [appm/fpy] 810 980 980 810 1080 1260 1230 1080 1490 1630 1600 1500

He production per Fe atom [appm/fpy] 165 200 200 165 220 260 250 220 310 335 330 310

Nuclear heating [W/g] ([W/cm3]) 1.24 (4.4) 1.67 (11.3) 1.53 (6.7) 1.25 (4.4) 1.80 (12.2) 1.96 (8.6) 1.86 (6.6) 1.80 (12.2) 2.07 (9.1) 2.19 (7.7) 2.54 (17.2) 2.07 (9.1)


Nuclear Responses in the IFMIF sub-systems Neutron energy fluxes in the IFMIF

Test Cell global model

IFMIF test cell sub-system

Neutron Flux, 1014 n/cm2/s

Damage (Element), dpa/fpy

Li-jet back Plate (BP) 15.0 66 (Fe) High Flux Test Module (HFTM) 7.3 20 - 55 (Fe) Univers. Test Machine (UTM) 3.5 11 (Fe) Tungsten Moderator (W) 2.0 1.1 (W) Tritium Release module (TRM) 1.1 2.4 (Fe), 3.5 (Be) Low Flux Test Module (LFTM) 0.61 0.65 (Fe) Front wall steel liner 0.01 0.004 (Fe)

10-6 10-5 10-4 10-3 10-2 10-1 100 101 102109

1011

1013

1015

1017

LFTM

Front Wall

TRM

UTMHFTMBP

Neu

tron

Flu

x,

1/cm

2 /MeV

/s

Neutron Energy, MeV

IFMIF: 40MeV 250mA

Neutron fluxes & dpa in the IFMIF components

Front wall Liner

Li-jet

C

WHFTM

UTM

TRM

LFTM

d-beam

Li inject tank

Li quench tank

Front wall Liner

Li-jet

C

WHFTM

UTM

TRM

LFTM

Front wall Liner

Li-jet

C

WHFTM

UTM

TRM

LFTM

d-beam

Li inject tank

Li quench tank

BP


Induced Radioactivity in the IFMIF sub-systems

γ- Dose vs. Cooling Time after 1 year runIFMIF Test Cell

Induced activity is assessed for every IFMIF Test Cell component

10-3 10-2 10-1 100 101 102 103 104 105 10610-6

10-4

10-2

100

102

104

106

W

LFTM

UTM

106ySS-316 & W, 1 year in IFMIF

TRM

BP

Hands-on Limit

Recycling Limit

104y100y1y30d1d

HFTM

Front Wall LinerC

onta

ct -

Dos

e R

ate,

Sv

/h

Time after shutdown, years


Activation analyses of Eurofer and SS-316 steels (long term irradiation in the IFMIF components)

γ- dose of steels after 10 years irradiationin Universal Test Machine (UTM) frame

Eurofer & SS-316 composition

Reduced contents of Al, Ni and Mo in Eurofer steel result in lower activation in comparison with SS-316

Element Content, wt. % Dominant Activation Eurofer SS-316 Reaction B 0.001 0.0002 C 0.105 N 0.018 O 0.010 Al 0.008 0.05 27Al(n,2n)26Al Si 0.006 0.4 P 0.004 S 0.003 Ti 0.008 0.15 V 0.20 Cr 9.00 17.5 Mn 0.42 1.8 Fe 88.98 65.16 54Fe(n,p)54Mn

56Fe(n,p)56Mn Co 0.005 0.03 Ni 0.005 12.3 58Ni(n,p)58Co

60Ni(n,p)60Co Cu 0.005 0.1 Nb 0.001 0.005 Mo 0.001 2.5 94Mo(n,p)94Nb Ta 0.07 181Ta(n,t)178nHf W 1.10

10-3 10-2 10-1 100 101 102 103 104 105 10610-7

10-5

10-3

10-1

101

103

Hands-on

106y

Recycling

Total (Eurofer)58Co

178nHf

26Al

UTM frame, 10 years60Co

94Nb

104y100y1y30d1d

54Mn56MnTotal (SS-316)

-dos

e ra

te,

Sv/

h

Time after shutdown, years


Transmutation analyses of Eurofer (HFTM/IFMIF vs. FW/DEMO)

Elemental transmutation may reach 30% per fpy

B(.

001)

C(.

105)

N(.

030)

O(.

010)

Al(

.010

)Si

(.05

0)P(

.005

)S(

.005

)T

i(.0

10)

V(.

200)

Cr(

9.00

)M

n(.0

40)

Fe(8

9.0)

Co(

.050

)N

i(.0

05)

Cu(

.005

)N

b(.0

01)

Mo(

.005

)T

a(.0

07)

W(1

.10)

-20

-10

0

10

20

30

Burn-up

Generation

Tra

nsm

utat

ion

rate

, %

/fpy

- IFMIF/HFTM - FPR/HCLL - FPR/HCPB


d-Li radioactive inventory (3H and 7Be) cross sections

and thick target yields

3H and 7Be yields in thick Li target

Li(d,x)3H and 7Be cross sections

0 5 10 15 20 25 30 35 40 45104

105

106

107

, - Dmitriev (1982) - Mukhammedov (1984), - Möllendorff (2002) - Baba (2002)

Li(d,x)3H6Li(d,n)7Be

IRAC/JAERILi(d,x)7Be

MCDeLicious/INPE-FZK

Ind

uced

Act

ivit

y,

Bq/A

/hou

r

Incident Deuteron Energy, MeV

0

20

40

60

80

100

120

0 10 20 30 400

100

200

300INPE-FZK

6Li(d,x)T

7Li(d,x)T

Cro

ss S

ecti

ons,

mb

Deuteron Energy, MeV

Eye guided

INPE-FZK

7Li(d,2n)7Be

6Li(d,n)7Be


Tritium and Be-7 Inventories in the IFMIF Li Loop

3H and 7Be production rates in Li-loop sub-systems

Geometry model of Test Cell& Li -loop

Loop component

Mass, kg Reaction Inventory Rate, g/fpy

d + Li 7Be 1.5 Li jet 1 d + Li 3H 6.0

n + Li 3H 0.4

Li injection tank 18 n + Li 3H 0.2 Li quench tank 1200 n + Li 3H 1.0 Li drain tubes 3 n + Li 3H 0.1

Total 3H 7.7

Front wall Liner

Li-jet

C

WHFTM

UTM

TRM

LFTM

d-beam

Li inject tank

Li quench tank

Front wall Liner

Li-jet

C

WHFTM

UTM

TRM

LFTM

Front wall Liner

Li-jet

C

WHFTM

UTM

TRM

LFTM

d-beam

Li inject tank

Li quench tank


d-Li gamma-ray source and IFMIF “photonics”

IFMIF: neutronics vs. photonics γ-ray spectrum in HFTM

0 10 20 30 40 5010-8

10-6

10-4

10-2

100

Primary -Source:Li(d,)Secondary -Source:

Li(n,x)

Primary -Source:Li(d,x)

Ed = 40 MeV

Phot

on Y

ield

, 1

010

/MeV

/C

Photon Energy, MeV

d-Li source Reaction Li(d,xn) Li(d,x)

Number per 1 d 0.072 n/d 0.012 /d Source Intensity (4) 1.1 1017 n/s 1.9 1016 /s Source Power (4) 131 kW 2.4 kW Mean Energy (4) 7.3 MeV 0.84 MeV

Lithium Target Back Plate (BP) Heating Density 23 W/cm3 2.6 W/cm3

High Flux Test Module (HFTM) Flux 5.9 1014 n/cm2/s 2.5 1013 /cm2/s

Heating Density 14.0 W/cm3 0.5 W/cm3


– Updated d-Li evaluated cross sections were validated for neutrons, tritium and beryllium-7 yields (uncertainties at the level of 10% are expected)

– No experimental data exist for g-ray yields – Detailed 3-d geometry model of the IFMIF test cell has been

implemented in the Monte Carlo neutronics calculations – Nuclear responses (dpa, heat and gas production) have been calculated

for principal IFMIF sub-systems.– 3H and 7Be radioactive inventories have been assessed for the whole

Li-loop– Activation and transmutation analyses has been performed for the

IFMIF test cell and main structural materials

Summary

Documents

IAEA Technical Meeting on IFMIF, Karlsruhe, 4-6 October 2005