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Neutrons For Science (NFS) at SPIRAL-2. X. Ledoux and the NFS collaboration. ● The spiral 2 project ● Neutron production modes ● Design ● Beam characteristics ● Irradiation facility ● Physics case. graphite. UCx. deuterons. neutrons. 40MeV; 5mA. SPIRAL-2. Spiral-2 Layout. - PowerPoint PPT Presentation
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Contact: [email protected], April 4, 2007
Neutrons For Science (NFS) at SPIRAL-2Neutrons For Science (NFS) at SPIRAL-2
● The spiral 2 project
● Neutron production modes
● Design
● Beam characteristics
● Irradiation facility
● Physics case
X. Ledoux and the NFS collaboration
Contact: [email protected], April 4, 2007
M. Jacquemet, GANIL Colloquium, Giens, june 2006
Spiral-2 Layout
Contact: [email protected], April 4, 2007
Beams delivered by the LINAG
LINear Accelerator of Ganil
Power at full intensity I=5mA, E=40 MeV P=200 kW
Challenge: radioprotection 1015 n.s
Converter composition
● Two sources
one for deuterons
one for heavy ions
● Two RFQs q/A=3
q/A=6 for heavy ions (by now optional)
● LINAG
F0 = 88 MHz T=11 ns
26 cavities
Burst width = 200 ps
● Main specifications :
5 mA of 40 MeV deuterons
1 mA for heavy ions at Emax=14,5 A.MeV
All details available on www.ganil.fr
Contact: [email protected], April 4, 2007
Neutron For Science
A working group was created to study :
The possible use of the LINAG beam to built a neutron facility
The Physics case realizable at NFS
The facility will be composed of two parts :
Neutron beam
Irradiation station
Means :
Deuteron and proton beams
Thin and thick converter
Dedicated room(s)
A letter of intents was presented to the Scientific Advisory Committee of SPIRAL 2
Contact: [email protected], April 4, 2007
Neutron spectra provided at NFS (1)
Deuteron break-up on Thick converter
E deut = 40 MeV
The deuteron are stopped in the converter (1cm)
Continuous beam <E> = 14 MeV
Be instead C converter allows to increase the flux by a factor of 2
Meulders et al., Phys. Med. Biol. (1975)vol 20 n°2, p235
⇒ Similar to IFMIF spectrum
Contact: [email protected], April 4, 2007
Neutron spectra provided at NFS (2)
Neutron production by 7Li(p,n)7Be reaction
Thin converter (1-3 mm)
Quasi-monokinetic beam
Ep = 3 – 33 MeV
En ≈ Ep –1,6 MeV
Schumacher et al.,NIMA421 (1999) p2843
7Li(p,n)7Be
Contact: [email protected], April 4, 2007
Neutron For Science Facility
Sample
Detector(s)
Converter cave
- Beam line extension
- Clearing magnet
- Beam dump
- Irradiation stations (n, p, d)
Experimental Hall- Beam(s) at 0° and 30° optional
- Collimator design ↔ beam quality
- Size (L l)ⅹ ≃ (30m ⅹ 6m)
time-of-flight measurement
measurement at desired distance
large experimental set-up
Contact: [email protected], April 4, 2007
Beam repetition rate
Requirement: differentiation of 2 neutrons with the ToF t and t+T
L(m) Eth (MeV) T(s) N Imax(A)
5 0.1 1 100 50
30 0.1 6 600 8
T 1 ≃ s
T 6 ≃ s
T 1 ≃ s
T 6 ≃ s
TLINAG = 11 ns
Take only one burst over N (f = F0/N)
- burst selector
- I = Imax / N, with Imax=5mA
Contact: [email protected], April 4, 2007
Energy resolution
L=30m and fast detector ⇒ high resolution measurement
HPGe detector ⇒ E/E < 5% for L=30 m
The neutron energy is measured by time-of-flight technique
Good resolution measurements require :
- A unique burst selector
- Burst duration on converter < 1ns (buncher might be needed)
t : Full time resolution :
td ≃ 1 ns scintillator
≃ 8 ns HPGe
tb ≃ 1 ns
E
E
t
t
L
L
12 2
22bd ttt
Contact: [email protected], April 4, 2007
N-tof : CERN,
Spallation,L=185 m,F=0.4Hz
GELINA : Geel,
Photofission, F=800Hz,30 m
Spiral-2 : high intensity high resolution
Comparison with other neutron beam facilities
Complementary to the existing facilities
• En: from 1 MeV to 40 MeV
• High flux ⇒ small samples
coincident experiments
• Reduced flash
Contact: [email protected], April 4, 2007
Comparison with other neutron beam facilities
● Disadvantages of NFS
- high frequency
- flux by burst smaller than n-tof or Gelina
- only fast neutrons (1-40 MeV)
●Advantages of NFS :
high average flux in the 1-40 MeV range :
- small samples
- coincident experiments
production mode :
- no high energy neutron (in comparison with spallation)
- reduced gamma flash (in comparison with photoreaction)
Hall size :
- desired distance between 5 and 30 m high flux or high resolution
- use of large set-up
Contact: [email protected], April 4, 2007
Measurement by activation technique
- Neutron induced reaction
The sample is put very close of the converter
White source <E> = 14 MeV
>5.1011n/s/cm2 for Id=50 A
Quasi-monoenergetic (Li converter on carbon back-up)
- Proton and Deuteron induced reaction
Two irradiation stations can be installed in the converter cave :
- Off-line activity measurement in a separate room
- Detectors for flux monitoring
→ Cross-section measurement :
Imax limited to 50 A- Low power deposition on converter < 2 kW
- Reduced activation « easy » sample manipulation
Contact: [email protected], April 4, 2007
Monoenergetic neutrons beam
• d + d → n + 3He Q = 3.27 MeV
- En(0 deg) = 3.2 –7.2 MeV for Ed= 0 - 4 MeV
- Gaseous or solid (TiD) targets
• d + T → n + 4He Q = 17.59 MeV
- En(0 deg) = 14 –20 MeV for Ed= 0 - 3.7 MeV
- only solid target (TiT)
Mono-energetic neutrons can be produced by the following reactions
Low energy deuteron beam (Ed < 4 MeV)
The neutron flux depend on the power the target can sustain
Contact: [email protected], April 4, 2007
Converter caveroof 1,5 mwalls 2 m
TOF room :wall thickness ≈ 50cmneutron beam dump at 0 degree
Light concrete: less activation than in concrete loaded with iron
Radioprotection simulations
Contact: [email protected], April 4, 2007
Radioprotection
Neutron dose calculation for 100 A d + Be (1 cm)Code PHITS (V. Blideanu)
Public area : D < 0,5 Sv/h
Contact: [email protected], April 4, 2007
Contact: [email protected], April 4, 2007
Possible implementation
Contact: [email protected], April 4, 2007
General Physics Case
Reactions induced by fast neutrons are of first importance in the following topics :
- Fission reactors of new generation
- Fusion technology
- Studies related to hybrid reactors (ADS)
- Validation of codes
- Nuclear medicine
- Development and characterization of new detectors
- Irradiation of chips and electronics structures used in space
Workshop and reports:
International Workshop on Neutrons for Science (NFS) at SPIRAL-2, GANIL, Caen, France; 13-14 December 2004. D. Ridikas et al, “Neutrons for Science (NfS) at SPIRAL-2”, Internal report DAPNIA report 05-30, Saclay, France (2005),
A. Plompen, “Nuclear Data Needs for Nuclear Energy (fission) and Possible Contributions of SPIRAL2”, 15th Colloque GANIL, Giens, France (2006)
U. Fischer, “Nuclear data needs for fusion technology and possible contribution by SPIRAL2”, 15th Colloque GANIL, Giens, France (2006).
Contact: [email protected], April 4, 2007
Neutron induced fission
• Need of data for fast neutron essentially for minor actinides
ADS, GEN IV reactors
Cross-section measurements
Neutron, gamma multiplicity and spectra
Fragment yields
• NFS short flight path → High flux
Small samples ( emitters)
Coincidence measurements
• Complementary to surrogate reactions
Limited to 10 MeV
Model dependence
• Study of the fission process
Continuous spectrum → continuous excitation energy
Coincidence experiment
(A,Z) fragment distribution
Contact: [email protected], April 4, 2007
(n,X) cross section measurements
• (n,xn) reactions
Maximum in the NFS energy range
Neutron multiplication
• (n,LCP)
Gazes and default production
Energy deposition in therapy
Composite particle prediction → no model works
• In-beam -ray spectroscopy
White source and quasi-monokinetic spectrum
(n,2n), (n,np), (n,) reactions
Use of large Ge array for - coincidence measurements
• Double differential measurements (n,xn), (n,LCP)
Few data exist between 20 and 50 MeV
Use of existing detection set-ups
56Fe(n,) cross sections in several data bases.
Incident energy (MeV)
(ba
rns)
Contact: [email protected], April 4, 2007
Cross-section measurement needed for fusion technology
0 10 20 30 40 5010-2
10-1
100
101
102
103
EAF-2005
p-D2O spectrum
d-Li spectrum
IEAF-2001
186W(n,n+)182mHf
, m
b
Neutron Energy, MeV
0 5 10 15 20 25 30 35 40 4510-3
10-2
10-1
100
Ditroi'00_Sig EAF20051_Nb93d2nMo92m
93Nb(d,2n)93mMo
Cro
ss S
ecti
on,
b
Deuteron Energy, MeV
EAF-2005.1
Ditroy'00
IFMIF and ITER need neutron and deuteron induced
reactions cross-section.
- Data scarce or not existing
- Large discrepancies between data bases
Material to be studied for IFMIF :
Al, Fe, Cr, Cu, Nb for cavities and beam transport elements
Be, C, O, N, Na, K, S, Ca, Fe, Cr, Ni for Li loop
• Cross-section measurement by activation technique
• 2 irradiation stations :
- Neutron induced reactions
- Proton and deuteron
• Imax limited to 50 A
- Power deposition on converter < 2 kW
- Reduced activation « easy » sample manipulation
Contact: [email protected], April 4, 2007
Summary
- White and quasi-monokinetic spectra in the 1-40 MeV range
- Neutron beams with high flux and good energy resolution
- Complementary to the existing n-tof facilities
- Irradiation stations for activation measurements (n, p, d)
- Intensity on the converter limited to 50 A
• reduced activation
• light converter design
- NFS is somewhat independent of RIB production
- Could start as soon as the LINAG is ready (2011)
The LINAG characteristics are particularly well adapted to a neutron facility at SPIRAL-2
Contact: [email protected], April 4, 2007
The NFS collaborationThe NFS collaboration
X. Ledoux1), M. Aïche2), G. Ban3), G. Barreau2), P. Baumann4), P. Bem5), V. Blideanu6), J. Blomgren7) , S.
Czajkowski2), P. Dessagne4), E. Dupont6), T. Ethvignot1), U. Fischer8), F. Gunsing6), B. Jacquot9), B.
Jurado2), M. Kerveno4), F. R. Lecolley3), J. L. Lecouey4), F. Negoita10), S. Oberstedt11), M. Petrascu10),
A.J.M. Plompen11), F. Rejmund9), D. Ridikas6), G. Rudolf4), O. Shcherbakov12), S.P. Simakov8), J. Taïeb1)
1) Service de Physique Nucléaire, CEA/DIF, BP 12, 91980 Bruyères-le-Châtel Cedex, France
2) Centre d’Etudes Nucléaires de Bordeaux-Gradignan, 33175 Gradignan, France
3) Laboratoire de Physique Corpusculaire, ISMRa et Université de Caen, CNRS/IN2P3,France
4) Institut Pluridisciplinaire Henri Curien, Strasbourg, France
5) Nuclear Physics Institute, 25068 Řež, Czech Republic
6) Centre d’Etudes Nucléaires de Saclay, DSM/DAPNIA, France
7) Department of Neutron Research, Uppsala University, Uppsala, Sweden
8) Forschungszentrum Karlsruhe, Institute for Reactor Safety, Karlsruhe, Germany
9) GANIL, CEA/CNRS, Caen, France
10) NIPNE, Bucharest, Romania
11) Institute for Reference Materials and Measurements, Geel, Belgium
12) PNPI, Gatchina, Russia