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FNG TUNGSTEN EXPERIMENT
1. Name of Experiment:
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FNG Benchmark Experiment on Tungsten (2001)
2. Purpose and Phenomena Tested:
----------------------------
The purpose is to validate the W cross sections in the European Fusion
File (EFF), as tungsten is a candidate material for high flux component
in the fusion reactor and its development is pursued in the European
Fusion Technology Program.
The experiment [1, 2] was performed at the 14 MeV Frascati Neutron
Generator (FNG).
3. Description of Source and Experimental Configuration:
----------------------------------------------------
The 14-MeV d-T Frascati Neutron Generator (FNG, [3]) was the neutron
source. The angular dependence of the source intensity is presented in
Figure 1 and in Table 1. The angular dependence of the source energy
distribution is shown in Figure 2 and is given in Table 2.
The geometry of the mock-up is outlined in Figure 4.
It consisted of a block of a tungsten alloy, DENSIMET, produced by PLANSEE,
in pieces of various shapes, assembled to obtain a size of about
42-47 cm (L) x 46.85 cm (H) and 49 cm in thickness and located in front
of the FNG target, 5.3 cm from the neutron source. Most of the material
(about 1.5 ton) is DENSIMET-176 type (92.3% W, 2.6% Fe, 4.2% Ni).
A layer of DENSIMET-180 (about 0.25 ton, 7 cm height, composition 95.0% W,
1.6% Fe, 3.4% Ni) was used in the central part of the block were the
measurements are done (Figs. 4-8), and contains the lateral access
channels (diameter 5.2 cm) for locating detectors of the various types
(activation foils, TLD holders, active spectrometers).
4. Measurement System:
------------------
The following quantities are measured :
a - Neutron reaction rates by activation foils
b - Nuclear heating by thermo-luminescent detectors (TLD-300)
Eight different reactions: 197Au(n,g), 55Mn(n,g), 115In(n,n’), 58Ni(n,p),
56Fe(n,p), 27Al(n,a), 58Ni(n,2n), 90Zr(n,2n) and 93Nb(n,2n) were used to
derive the neutron flux, from low energy up to the fusion neutron peak.
The reaction rates were measured in four experimental positions at different
depths from the block surface, using the radiometric techniques based upon
the use of absolutely calibrated HPGe detectors. During the activation foil
measurements, the lateral access channels were completely closed by means of
4 ad hoc cylinders made of DENSIMET – 180, a thin slot was realised (4.4 mm)
to locate activation foils in position, using a thin Al holder. The foils
were irradiated in three irradiations: in the first one Zr, Al and Mn foils
were irradiated, the foils arrangement is described in the MCNP input file
ZrAlMn.mcp; in the second one Nb, Ni and Au foils were irradiated, the
foils arrangement is described in NbNiAu.mcp; in the last irradiation
Fe and In foils were irradiated, the foils arrangement is described in
FeIn.mcp. The experimental results are given in Table 4.
Gamma heating was measured using TLD-300 dosimeters (CaF2:Tm). TLDs
calibration was performed using Co-60 secondary standard, from 50 mGy up to
4 Gy in air, converted into absorbed dose in TLD-300 using the photon energy
attenuation coefficients from Hubble [4].
Seven TLDs chips (3.2x3.2x0.9 mm3 each) were located in each experimental
position, using the same experimental arrangement as for the activation foils,
and enclosed in a perspex holder 1 mm thick. The experimental arrangement is
described in the MCNP input file mcnp_tld.inp.The measured dose in TLD-300 is
given in Table 5.
5. Description of Results and Analysis:
-----------------------------------
The experiment was analysed by using the Monte Carlo code MCNP-4C [2, 5] using
for W, Fe and Ni the point-wise cross sections derived from EFF-2.4 and
FENDL-2.0 [6]. In the case of EFF calculation, the Fe cross section were
taken from EFF-3.0. The MCNP model of the experimental set-up was is given
in ZrAlMn.mcp, NbNiAu.mcp and FeIn.mcp for the activation foils measurements,
and in mcnp_tld.inp for the TLD measurements. The track length estimator was
used (tally 4 of MCNP) for fluxes and reaction rates calculation, while the
gamma heating is calculated from the gamma energy deposition over the TLD
cells (tally 6 of MCNP). All dosimetric reactions needed for the calculation
of reaction rates were taken from IRDF-90.2 library [7]. The calculated
reaction rates and gamma doses (C) are given in Tables 6 and 7 respectively,
together with the MCNP statistical uncertainty.
Deterministic transport and cross section sensitivity/uncertainty analyses
using the DORT, TWODANT and SUSD3D codes are presented in [8], [9] and [10].
The following input data used in these analyses are included here:
- TRANSX (cross section preparation),
- GRTUNCL and DORT (uncollided/first collision source and transport
calculation)
- TWODANT (neutron transport using first collision approach).
The 2-dimensional cylindrical geometry model used in the DORT and TWODANT
deterministic transport calculations is shown in Figure 10.
6. Special Features:
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None
7. Author/Organizer:
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Experiment and analysis:
P. Batistoni, M. Angelone, M. Pillon, L. Petrizzi
ENEA
Centro Ricerche Energie Frascati
UTS Fusione
Via E. Fermi 27
C.P. 65
I-00044 Frascati (Rome)
Italy
Compiler of data for Sinbad:
P. Batistoni
ENEA
Centro Ricerche Energie Frascati
UTS Fusione
Via E. Fermi 27
C.P. 65
I-00044 Frascati (Rome)
Italy
Reviewer of compiled data:
I. Kodeli
OECD/NEA, 12 bd des Iles, 92130 Issy les Moulineaux, France
Acknowledgement
---------------
The experiment and the corresponding analysis was performed in the framework
of the EFDA (European Fusion Development Agreement) Task (TTMN-002-2002).
8. Availability:
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Unrestricted
9. References:
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[1] P. Batistoni, M. Angelone, L. Petrizzi, M. Pillon, Measurements
and Analysis of Neutron Reaction Rates and of Gamma Heating in
Tungsten, MA-NE-R-003, ENEA, Dec. 2002
[2] P.Batistoni, M. Angelone, L. Petrizzi and M.Pillon, Neutronics
Benchmark Experiment on Tungsten, presented at ICFRM-11 (2003),
to be published in Journal of Nuclear Materials
[3] M. Martone, M. Angelone, M. Pillon, The 14 MeV Frascati Neutron
Generator, Journal of Nuclear Materials 212-215 (1994) 1661-1664;
[4] J.H. Hubble, Photon mass attenuation and energy-absorption
coefficients from 1 keV up to 20 MeV, Int. J. Appl. Rad. Isot.
33 (1982) 1269
[5] Briesmeister, J. F. (Ed.), MCNP - A general Monte Carlo
n-particle transport code, version 4C, Report LA12625, Los
Alamos, September 1999.
[6] M. Herman, A. B. Pashchenko, Extension and improvement of the
FENDL library for fusion applications (FENDL-2), Report
INDC(NDS)-373, IAEA, Vienna, 1997.
[7] N. P. Kocherov, P. K. McLaughlin, The International Reactor
Dosimetry File (IRDF-90), Report IAEA-NDS-141, Rev. 2, Oct. 1993.
[8] I. Kodeli, Analysis of Benchmark Experiment on Tungsten Using
DORT, TWODANT and SUSD3D Deterministic Analysis Tools,
EFF Meeting, Issy-les-Moulinaux (Jan. 2003)
[9] I. Kodeli, Analysis of FNG Benchmark Experiment on Tungsten Using DORT,
TWODANT and SUSD3D Deterministic Codes, EFFDOC-867 (April 2003)
[10] I. Kodeli, Tungsten Benchmark Experiments: Re-analysis Using JENDL-3.3,
EFFDOC-885 (Nov. 2003)
[11] I. Kodeli, Cross-Section Sensitivity Analysis of 14 MeV Neutron
Benchmark Experiment on Tungsten, Journal of Nuclear Materials,
Vol. 329-333, Part.1, P. 717-720 (2004)
10. Data and Format:
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FILE NAME bytes Content
---- ----------- ------ -------
1 fngw-a.htm 13,300 This information file
2 fngw-e.htm 26,634 Description of Experiment
3 fngw-c.htm 6,233 Transport calculations - description & results
4 source.for 45,178 FORTRAN subroutine for MCNP source description
5 FeIn.mcp 89,670 3-D model for MCNP-4C calculation of
activation reaction rates (Fe and In foils)
6 NbNiAu.mcp 91,581 3-D model for MCNP-4C calculation of
activation reaction rates (Nb, Ni and Au foils)
7 ZrAlMn.mcp 91,649 3-D model for MCNP-4C calculation of
activation reaction rates (Z, Al and Mn foils)
8 mcnp_tld.inp 132,050 3-D model for MCNP-4C calculation of gamma dose rates
9 trx-w.inp 1,027 Input data for TRANSX cross-section preparation
10 dort-w.inp 9,235 Input data for GRTUNCL first collision source and
DORT transport codes
11 2dant-w.inp 12,663 Input data for TWODANT transport code
12 fig1.gif 5,242 Fig. 1: Angular dependence of the source
13 fig2.gif 9.505 Fig. 2: Energy/angular dependence of the source
14 fig3.gif 9,633 Fig. 3: Geometry of FNG target
15 fig4.gif 10,267 Fig. 4: Y-Z view of FNG-W mock-up with detectors (X=0)
16 fig5.gif 12,247 Fig. 5: Y-Z view of FNG-W (X=0)
17 fig6.gif 9,761 Fig. 6: X-Y view of FNG-W (-3.5 cm < Z < 3.5 cm)
18 fig7.gif 7,133 Fig. 7: X-Y view of FNG-W (-15.5 cm < Z < -3.5 cm)
and (3.5 cm cm < Z < 15.5 cm)
19 fig8.gif 11,982 Fig. 8: X-Z view of the mock-up (Y=0)
20 fig9.gif 5,636 Fig. 9: Geometry of TLD detector
21 fig10.jpg 88,233 Fig. 10: Geometry model used in codes DORT and TWODANT
22 enea-w.pdf 709,900 Reference 1
23 kodeli-w.pdf 311,454 Reference 8
24 eff-867.pdf 376,727 Reference 9
25 eff-885.pdf 170,688 Reference 10
26 kyoto03.pdf 201,723 Reference 11
Files fngw-e.htm and fngw-c.htm contain the following tables:
Tab. 1: Angular dependence of the source
Tab. 2: Angular/energy dependence of the source energy distribution
Tab. 3: The chemical composition and the density of DENSIMET-176 and
of DENSIMET – 180
Tab. 4: Measured neutron reaction rates
Tab. 5: Measured absorbed dose in TLD
Tab. 6: MCNP calculated reaction rates - C/E ratios
Tab. 7: MCNP calculated absorbed dose in TLD - C/E ratios
The figures are given in gif format.
SINBAD Benchmark Generation Date: 1/2004
SINBAD Benchmark Last Update: 4/2006
