Associazione EURATOM ENEA sulla Fusione

IEA International workshop on Fusion Neutronics18 October 2001, Baden-Baden (Germany)

ENEA Activity in 2001 P. Batistoni

Shut Down Dose Rate Experiment for ITER (T-426)

Experimental Validation of EFF/EAF Nuclear Data Libraries (EU Technology Program TTMN-002)

Decay heat measurements on EUROFER and other materials Benchmark experiment on SiC

Objective : verify shut down dose rate calculation for ITER out-vessel, in-cryostat for tcool 1 monthMock-up irradiated at FNG (3 days) to have a detectable dose rate (ENEA, TUD, FZK)

Associazione EURATOM ENEA sulla Fusione

ITER Task T426 – EU SHUT DOWN DOSE RATE EXP. for ITER

0

10000

20000

30000

40000

50000

60000

0.0E+00 5.0E+04 1.0E+05 1.5E+05 2.0E+05

Time (s)

Cou

nts

FNG, 8-9-10 May 2000Total yield 1. 815E15 neutrons

9.45E14 neutrons in 2.97e4 s

2.98e14 neut. in 1.23 E4 s

1.22E14 neut. in 8406 s

4.50E14 neutrons in 1.43e4 s

ITER Task T426 – EU SHUT DOWN DOSE RATE EXP. for ITER – ANALYSIS

R2S method D1S method

1.E-07

1.E-06

1.E-05

1.E-03 1.E-02 1.E-01 1.E+00Time after irradiation (y)

Sv/

h Measured Doserate (G-M)

Measured Doserate (TLD)

R2S (FENDL-2/A)

D1S (FENDL-2/MC)

D1S (FENDL-2/A)

15 days1 month

7 days

2 months

1 day

4.0E-01

5.0E-01

6.0E-01

7.0E-01

8.0E-01

9.0E-01

1.0E+00

1.1E+00

1.2E+00

1.3E+00

1.00E-03 1.00E-02 1.00E-01 1.00E+00Time after irradiation (years)

C/E

R2S (FENDL-2/A)

D1S (FENDL-2/A)

D1S (FENDL-2/MC)

CONCLUSIONS

The shut down dose rate outside the ITER vessel is calculated by 2-step method R2S (MCNP/FISPACT) and by 1-step method D1S (MCNP-modified), using and FENDL-2 data, within 15% from a few days up to 2 months of decay time

Associazione EURATOM ENEA sulla Fusione

ITER Task T426 – EU SHUT DOWN DOSE RATE EXP. for ITER – RESULTS

Ni-58 (n,p) Co-58

0.7

0.8

0.9

1

1.1

1.2

1.3

0 1 2 3 4 5 6 7Foil position

C/E

R2S-FENDL/A-2

D1S-IRDF-90.2 or FENDL/MC-2

Ni-58(n,2n)Ni-57

0.7

0.8

0.9

1

1.1

1.2

1.3

0 1 2 3 4 5 6 7Foil position

C/E

R2S-FENDL/A-2

D1S-FENDL/MC-2

MCNP/IRDF-90.2

Ni-58(n,p): using FISPACT with FENDL/A–2 (R2S), C/E slightly higher than unity, while those obtained with direct MCNP calculation (D1S) using IRDF-90 and FENDL/MC–2 generally lower and in better agreement with the measurements.

Ni-58(n,2n): using the direct MCNP calculation (D1S) with IRDF-90 and FENDL/MC–2, C/E very close to unity. Using FISPACT with FENDL/A–2 (R2S), C/E about 1 - 3% lower than in the previous case.

The Ni-58(n,p)Co-58 and Ni-58(n,2n)Ni-57 reaction rates were directly measured during irradiation, and calculated using both the R2S method and the D1S method

0

10

20

30

40

50

60

70

80

90

100

1.E-04 1.E-03 1.E-02 1.E-01 1.E+00

Time after irradiation (Y)

Co

ntr

ibu

tio

n t

o t

ota

l d

ore

rat

e (%

)

Mn-56

Ni-57

Co-58

Fe-59

Mo-99

Mn-54

Co-60

Cr-51

Cu-64

SUM

ITER Task T426 – EU SHUT DOWN DOSE RATE EXP. for ITER – RESULTS

EU Fusion Technology Program – Nuclear Data Experimental validation of EAF activation cross sections

1 10 100 1000

0.0

0.5

1.0

1.5

Beta power

Gamma power

C/E

Decay time (hours)

• Beta power• Gamma power

Decay time (hours)

1.5

C/E1.0

0.5

0.0

EUROFER

Detecting system developed to measure simultaneously the total activity of a neutron irradiated material and the electron and photon decay heats

Activation/decay heat in EUROFER- and -decay heat measured up to tcool ~ 20 days,- activity measured up to several months of cooling timeDeficencies in beta decay heat identified in the comparison with EAF predictions

Associazione EURATOM ENEA sulla Fusione

Decay heat in 12 materials (Cu, Ag, Sn, Cd, Mg, Hf, Mo, Al, Ti, Ni, W, Re)

- and -decay heat measured and compared with EAF predictions

Some deficencies identified in EAF

Activation/decay heat in Cr and other materials is in progress (2001 activity)

EU Fusion Technology Program – Nuclear Data Experimental validation of EAF activation cross sections

Associazione EURATOM ENEA sulla Fusione

EU Fusion Technology Program – Nuclear Data

Validation of EFF cross sections for advanced materials

SiC EXPERIMENT at FNG (2000-2001) (ENEA, TUD,FZK, IJS)Objective Provide validation of EFF data for Silicon carbide which is a candidate low activation material for the fusion reactor, and is considered for development in the European Fusion Technology Program

.

Associazione EURATOM ENEA sulla Fusione

(SiC block on loan from JAERI within IEA collaboration)

Measurements (already completed)

• neutron and gamma spectra (TUD)•Activation (ENEA)•Gamma heating (ENEA)

Analysis (in progress)

• C/E for all measured quantities for EFF (and FENDL-2) libraries•Sensitivity /uncertainty analysis based on 3D MC and 2D deterministic approaches

Activaton Measurements

1.E-08

1.E-07

1.E-06

1.E-05

1.E-04

1.E-03

0 10 20 30 40 50 60 70

Penetration depth (cm)

Act

ivat

ed n

ucle

i/nuc

lei/1

e24

Nb

Al

Ni

Au

Nuclear heating measurements

1.00E-17

1.00E-16

1.00E-15

1.00E-14

0 10 20 30 40 50 60 70

Penetration depth (cm)

Gy/

n

TLD-1

TLD-2

EU Fusion Technology Program – Nuclear Data

Validation of EFF cross sections – SiC experiment

Associazione EURATOM ENEA sulla Fusione

0.40.50.60.70.80.91.01.11.21.31.41.51.61.7

0 10 20 30 40 50 60

Penetration depth (cm)

C/E

Nb-EFFAl-EFFNi-EFFNb-FENAl-FENNI-EFF

EU Fusion Technology Program – Nuclear Data

Validation of EFF cross sections – SiC experiment

Associazione EURATOM ENEA sulla Fusione

Preliminary analysis on fast neutron flux measurements show a significant difference between EFF(2.4) and FENDL-2

Analysis will be performed with new Si and C evaluation in EFF as soon as processed data will be available

Analysis could also be performed using JENDL-FF in the frame of IEA collaboration

Benchmark experiment on W planned in 2002