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The 14 MeV Frascati Neutron Generator (FNG)

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Presentation on theme: "The 14 MeV Frascati Neutron Generator (FNG)"— Presentation transcript:

1 The 14 MeV Frascati Neutron Generator (FNG)
HeRe in Italy, ENEA Centro Ricerche Frascati December 2-3, 2013 The 14 MeV Frascati Neutron Generator (FNG) Maurizio Angelone Associazione ENEA-EURATOM sulla Fusione Via E. Fermi, 45 – Frascati (Italy)

2 Introduction The Frascati Neutron Generator (FNG) started operations in November making available 14 MeV neutrons at a medium intensity (10^11n/s) to EU Fusion Community. The Fusion Neutronics community strongly supported the idea of international collaboration in neutronics experiments, in data base & code improvement and in development of (new) experimental techniques. FNG has been designed at ENEA. FNG has been realized by ENEA (Fusion Division) at is own expense. FNG has been (and is) extensively used for performing benchmarks and mock-up experiments of interest to Fusion neutronics to validate Nuclear Data and Codes. A number of activities in various fields (& collaborations) carried out at FNG so far

3 Miscellaneous Activities at FNG
Apart from the Benchmarks and Mock-yup experiment for fusion neutronics, FNG is used for several collaboration/service in many different fields: Test of electronics chips, components, cards, software etc. Irradiation of “in vivo” samples (e.g. cells, mice, vegetables etc. for radiation induced effects  space dosimetry) Test of new detectors (e.g. diamond, GEM, RPC, etc.) Detector calibration (e.g. Xenon detector for DAMA exp.) Efficiency of dosimeters (for dosimetry, e.g. CR-39)

4 The Facility The 14 MeV Frascati Neutron Generator (FNG) is in operation since November 1992. FNG is a linear electrostatic accelerator in which up to 1 mA D+ ions are accelerated onto a tritiated target to produce up to 1.0E+11 n/s 14 MeV neutrons via the nuclear fusion reaction : D+T a+n (Q=17.4 MeV) The FNG neutron source is almost isotropic, its absolute strenght is calibrated at ±3% using the Associated Particle method. Using a deuterated target also 2.5 MeV neutrons can be produced by the D+D n+3He reaction The maximum strenght is < 1.0E+09 n/s calibrated by activation methods (Indium foils) 4

5 FNG Parameters Operation continuous or pulse mode (tp = 6s minimum)
D-T operation D-D operation Max neutron yield 1*1011 n/s 1*109 n/s Max neutron flux  volume 5*109 neutrons cm-2 s-1  1cm3 5*107 neutrons cm-2 s-1  1cm3 Max irradiation volume  flux A few cm3  107/s/(4**m2) A few cm3  105/s/(4**m2) Max irradiation time- targets 25 hours (one target) continuous Average utilization/year > 150 hours/years Free time available for irradiation 200 hours/years Maximum achievable fluence 1*1015 n/cm2 on a 1 cm3 sample 1*1013 n/cm2 on a 1 cm3 sample Operation continuous or pulse mode (tp = 6s minimum)

6 FNG MAIN COMPONENTS H.V. TERMINAL ION SOURCE
ION SOURCE CHAMBER –EINZ LENS BENDING MAGNET QUADRUPOLES ACCELERATOR TUBE VACUUM PUMP TARGET

7

8 FNG A neutron generator to be reliable must have its neutron source absolutely calibrated at the state-of-the-art technique  mandatory for performing benchmarks and mock-up experiments

9 Absolute source calibration
Ratio activation measurements to SSD using the 27Al(n,)24Na ad 92Nb(n,n’)92mNb reactions Neutron yield is monitored measuring the alpha particles from the T(d,n) with a Silicon Surface barrier Detector (SSD)

10 Experimental Calibration & simulation using MCNP
U-238 F.C response

11 SOURCE SPECTRUM SIMULATION
D-T and D-D neutron energy spectra are properly modelled as a two body reaction Beam energy goes from Emax to 0 during deuteron slowing down (thick target!) Relativistic formula used in the latest version

12 A “ad hoc” source routine was implemented in MCNP.
This routine takes in to account all the physical aspects of the neutron production from the beam-target interaction, including ions scattering, fusion cross-section anisotropy, etc. In the MCNP geometry the target holder and the used detectors dimensions and materials are also described. Pd = point detector Cf = cell flux estimator The Source routine was developed by ENEA Frascati and Institut Jozef Stefan (JSI) in Ljubljana and is available in SINBAD database at NEA. Latest version up to 10 MeV beam energy (not yet in SINBAD)

13 Spectrum with Diamond detector at 90°°
The Source routine was recently validate using Diamond Detectors located at various angles around FNG target Spectrum with Diamond detector at 90°° FNG 90° Diamond Detector

14 CVD diamond 0°respect the beam. (Beam energy 230 keV)

15 CVD diamond 0° respect the beam. (Beam energy 290 keV)

16 Experimental techniques in the FNG laboratories :
Activation technique X- and g-ray spectroscopy Dosimetry Decay heat detection system

17 Main Experimental Tools
Two HPGe detectors absolutely calibrated for g-ray spectroscopy plus a number of activation foils. TOLEDO TLD reader plus several types of TLD detectors (LiF, GR-206, GR-207, TLD-300); g and n dose separation GM tubes for g-dose measurements Two F.C. detectors (U-238 and U-235) Scintillators CVD diamond detectors for thermal and fast neutrons, X-ray and UV detection. MCNP and MCNPX codes for modelling and testing the experiments. Codes for neutron spectrum unfolding

18 Thank You !


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