1. magnetic confinement - ENEA - Fusione

3. FUSION TECHNOLOGY 103
3.12 Safety and Environment, Power
Plant Studies and Socio-Economics
800
Neutron transport and materials activation
Pressure (kPa)
600
400
200
ISAS pre-test
Experiment
ISAS post-test
The code package updating, completed in November
2000, was released to the OECD-NEA Data Bank.
Validation of the ANITA-2000 code package continued
[3.60, 3.61] by comparing calculations with the
experiments performed at the Fusion Neutronics Source
(FNS), JAERI, Tokai, Japan.
0
0 20 40 60 80 100
Time (s)
Fig. 3.44 – Plasma chamber pressure for ICE case
7 (ISAS).
The material samples were irradiated by a 14-MeV
neutron flux in two series lasting 5 min and 7 h,
respectively. The neutron energy spectrum and neutron
source intensity of the experimental irradiation, as well as
the sample compositions, were provided by JAERI. A 175
energy-level neutron flux distribution was considered.
[3.60] D.G. Cepraga, G.
Cambi, M. Frisoni,
ANITA-2000 activation
code package. Part II :
code validation, ENEA
FUS-TN-SA-SE-R-020
(2001)
[3.61] D.G. Cepraga et al.,
Decay heat estimate for
fusion relevant materials
based on EAF-99 and
FENDL/A-2 libraries in
comparison with FNS-
Jaeri experiments, EFF-
DOC-797, EFF/EAF
Monitoring Meeting,
NEA-OECD (Paris 2001)
The European Activation File EAF99, the Fusion Evaluated Nuclear Data Library
FENDL/A-2) and the decay data library for fusion applications FENDL/D-2 were
used.
Tables 3.VI and 3.VII summarise the experiment-calculation comparison, by range of
discrepancies, for the 5-m and the 7-h irradiation scenarios, respectively, and for both
activation libraries.
As a general conclusion, it can be observed that, for the experimental irradiation
scenario analysed, EAF99 generally provides a better agreement with the experiment
than FENDL/A-2.
Table 3.VI - Summary of calculation-experiment comparison (C-E)/E for
samples irradiated for 5 min.
(C-E)/E EAF99 FENDL/A-2
50 % B4C, BaCO 3 , Bi, Cr, Na 2 CO 3 , B4C, BaCO 3 , Bi, CaO, Cr,
SiO 2 , Y2O 3 Na 2 CO 3 , SiO 2 , Ta, Y2O 3
Table 3.VII - Summary of calculation-experiment comparison (C-E)/E for
samples irradiated for 7 h
(C-E)/E EAF99 FENDL/A-2
< 10% Co,Mn, Nb, NiCr, Ni, Re, S, SrCO 3 , Co, Mn, Nb, NiCr, Ni, Re, S, SrCO 3 ,
SS-304, Ti, Zr, Inconel, SS-316 SS-304, Ti, Zr, Inconel, SS-316
10 to 50
%
BaCO 3 , CaO, Fe, Mo, Na 2 CO 3 ,
SnO2, Ta, V,Y 2 O 3 , Cu
BaCO 3 , CaO, Fe, Mo, Na 2 CO 3 ,
SnO 2 , V, Y 2 O 3 , Cu
> 50 % Al, Bi, Cr, K 2 CO 3 , Pb Al, Bi, Cr, K 2 CO 3 , Pb, Ta