Principles of neutron TOF cross section measurements
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1 Principles of neutron TOF cross section measurements J. Heyse, C. Paradela, P. Schillebeeckx EC JRC IRMM Standards for Nuclear Safety, Security and Safeguards (SN3S) H.I. Kim Korea Atomic Energy Research Institute Nuclear Data Center
2 Neutron induced reactions Neutron + A X
3 Neutron induced reactions Neutron + A X A+1 X
4 Neutron induced reactions elastic scattering (n,n) Neutron + A X A+1 X radiative capture (n,) fission (n,f) inelastic scattering (n,n ) other reactions (n,p), (n,d), (n,α)
5 Neutron induced reaction cross section 1 H 3 10 Cross section is a measure for the interaction probability Li B Cross sections strongly depend on: 0 Total cross section / b Co target nucleus incoming neutron energy Xe Pb Dedicated facilities required depending on energy region of interest U 0 10 thermal energy resonance region continuum 38 U Pu Neutron energy / ev
6 Production and use of nuclear data
7 (d n / dlne n ) / (cm - s -1 ) (d n / dlne n ) / (cm - s -1 ) Neutron energy spectrum Reactor Neutron induced fission ADS : E p = 600 MeV Spallation reactions 0.3 fast thermal 0.4 ADS-spectrum for E p = 600 MeV Neutron Energy / ev Neutron Energy / ev
8 (n,) / barn Neutron facilities at JRC-IRMM GELINA Tc(n,) cross section 99 Tc + n (n,) Van de Graaff White neutron source + Time-of-flight (TOF) Neutron Energy / ev Quasi mono-energetic neutrons through (cp,n) reactions
9 (n,) / barn Neutron facilities at JRC-IRMM Tc(n,) cross section 99 Tc + n (n,) Van de Graaff Neutron Energy / ev Quasi mono-energetic neutrons through (cp,n) reactions
10 Quasi mono-energetic neutron beams Van de Graaff
11 Charged particle induced neutron reactions quasi mono-energetic neutrons produced via charged particle induced nuclear reactions n e.g. T(d,n) 4 He d a 7 MV VDG - accelerator DC (I p,d < 50 A), Pulsed beam available (1 ns) 6 beam lines fast rabbit systems (T 1/ > 1s) : activation 7 Li(p,n) 7 Be E n : MeV T(p,n) 3 He E n : 0-6. MeV D(d,n) 3 He E n : MeV T(d,n) 4 He E n : MeV
12 Charged particle induced neutron reactions
13 Charged particle induced neutron reactions
14 (n,) / barn Neutron facilities at JRC-IRMM 99 Tc(n,) cross section Tc + n (n,) Neutron Energy / ev
15 (n,) / barn Neutron facilities at JRC-IRMM GELINA 99 Tc(n,) cross section Tc + n (n,) White neutron source + Time-of-flight (TOF) Neutron Energy / ev
16 TOF - Facility GELINA GELINA
17 GELINA (Geel Electron LINear Accelerator) Pulsed white neutron source (10 mev < E n < 0 MeV) FLIGHT PATHS NORD Pulse frequency 50Hz 800 Hz ELECTRON LINAC Neutron energy : time of flight (TOF) Multi-user facility: 10 flight paths (10 m m) TARGET HALL FLIGHT PATHS SOUTH Measurement stations with special equipment to perform: Total cross section measurements Partial cross section measurements
18 GELINA : neutron production NEUTRON FLIGHT PATHS e - accelerated to E e-,max 140 MeV Bremsstrahlung in U-target (rotating & cooled with liquid Hg) (, n), (, f ) in U-target NEUTRON TARGET NEUTRON MODERATOR ELECTRON BEAMLINE EXIT Low energy neutrons by moderation (water moderator in Be-canning)
19 GELINA : neutron production SHIELDING for MODERATED SPECTRUM SHIELDING for FAST SPECTRUM d n /dlne n / (cm - s -1 ) 10 5 GELINA 30 m 800 Hz Exp. Mod. Fast MCNP Mod. Fast Neutron Energy / ev
20 Time-of-flight technique Target- moderator assembly L Detector Sample
21 Time-of-flight technique Target- moderator assembly L Detector pulsed e - - beam Sample
22 Time-of-flight technique Target- moderator assembly L Detector pulsed e - - beam v Sample
23 Time-of-flight technique Target- moderator assembly L Detector pulsed e - - beam v Sample
24 Time-of-flight technique Target- moderator assembly L Detector pulsed e - - beam v Sample T 0 t (T s T 0 ) T s
25 Time-of-flight technique Target- moderator assembly L Detector pulsed e - - beam v Sample T 0 t (T s T 0 ) T s v L t
26 Time-of-flight technique Target- moderator assembly L Detector pulsed e - - beam v Sample T 0 t (T s T 0 ) T s v L t E mc ( 1) 1 mv
27 Time-of-flight technique Target- moderator assembly L Detector Sample
28 Time-of-flight technique Target- moderator assembly L Detector pulsed e - - beam Sample T 0
29 Time-of-flight technique Target- moderator assembly L Detector pulsed e - - beam v 0 Sample T 0
30 Time-of-flight technique Target- moderator assembly L Detector pulsed e - - beam T 0 v 1 Sample
31 Time-of-flight technique Target- moderator assembly L Detector pulsed e - - beam v Sample T 0
32 Time-of-flight technique Target- moderator assembly L Detector pulsed e - - beam v 3 Sample T 0
33 Time-of-flight technique Target- moderator assembly L Detector pulsed e - - beam v Sample T 0 t m = (T s T 0 ) T s
34 Time-of-flight technique Target- moderator assembly L Detector pulsed e - - beam v Sample T 0 t m = (T s T 0 ) + t o T s t 0 : time-offset
35 Time-of-flight technique Target- moderator assembly L Detector pulsed e - - beam v Sample T 0 t m = (T s T 0 ) + t o T s t 0 : time-offset determined by -flash L c (T s T 0 ) t 0
36 Time-of-flight technique Target- moderator assembly L Detector pulsed e - - beam v Sample T 0 t m = (T s T 0 ) + t o T s v L t
37 Time-of-flight technique Target- moderator assembly L Detector pulsed e - - beam v Sample T 0 t m = (T s T 0 ) + t o t = t m ( t t + t d ) T s v L t
38 Time-of-flight technique Target- moderator assembly L Detector pulsed e - - beam v Sample T 0 t m = (T s T 0 ) + t o t = t m ( t t + t d ) T s v L t E mc ( 1) 1 mv
39 Yield Theoretical capture yield Fe 1.15 kev resonance D = R = 0 Area density : at / barn Y tot (1 e n tot ) Neutron Energy / ev
40 Yield + Doppler Fe 1.15 kev resonance Area density : at / barn D = R = 0 D (kt = 5 mev) Y tot (1 e n tot (E) de' S(E') (E E' ) ) (E) D 1 de' e E' E D E' E (E') D 4 Ek m X B T /m n Neutron Energy / ev FWHM ln D
41 Yield + Doppler + Response Fe 1.15 kev resonance Area density : at / barn D = R = 0 D (kt = 5 mev) Y tot (1 e n tot (E) de' S(E') (E E' ) ) R for L = 60 m Y exp R(t,E)Y (E)dE R(t,E)dE L = 60 m E E L L t t Neutron Energy / ev
42 Yield Experimental observable FWHM D with - Total resonance width R x FWHM = Exp. Analytical (REFIT) MCNP R = D = = 43 ev 4 ev 15 ev ev - R Experimental resolution D Doppler broadening Neutron energy / ev
43 Yield Experimental observable FWHM D with - Total resonance width R x FWHM = Exp. Analytical (REFIT) MCNP R = D = = 43 ev 4 ev 15 ev ev - R Experimental resolution D Doppler broadening Neutron energy / ev
44 Time-of-flight technique: experimental resolution L v t t = (T s T 0 ) + t o ( t t +t d ) L v T 0 T s
45 Time-of-flight technique: experimental resolution v L t v v t t L L t = (T s T 0 ) + t o ( t t +t d ) L v T 0 T s
46 Time-of-flight technique: experimental resolution v L 1 E mc ( 1) mv v t L t v t L t = (T s T 0 ) + t o ( t t +t d ) E E (1 ) v v v v L v T 0 T s
47 Time-of-flight technique: experimental resolution v L 1 E mc ( 1) mv v t L t v t L t = (T s T 0 ) + t o ( t t +t d ) E E (1 ) v v v v L v T 0 T s
48 Time-of-flight technique: experimental resolution v L 1 E mc ( 1) mv v t L t v t L t = (T s T 0 ) + t o ( t t +t d ) E E (1 ) v v v v L L (~1 mm) v t - Initial burst T 0 T 0 T s - Time resolution detector & electronics T s - Neutron transport in target - moderator t t - Neutron transport in detector t d
49 Time-of-flight technique: experimental resolution t = (T s T 0 ) + t o ( t t +t d ) t Initial burst T 0 Time resolution detector & electronics Neutron transport in target - moderator Neutron transport in detector T s t t t d
50 Time-of-flight technique: experimental resolution t = (T s T 0 ) + t o ( t t +t d ) t Initial burst T 0 Time resolution detector & electronics Neutron transport in target - moderator Neutron transport in detector T s t t t d
51 Counts Resolution: initial burst (T 0 ) Single burst : mostly normal (Gaussian) distribution GELINA : T 0 = ns (FWHM) ORELA : T 0 = 4 ns (FWHM) ntof : T 0 = 8 ns (FWHM) Double pulse structure : ISIS J-PARC Exp (30037) Fit ISIS Gaussian response P P 1 = 318 ns FWHM = 60 n TOF / s
52 Time-of-flight technique: experimental resolution t = (T s T 0 ) + t o ( t t +t d ) t Initial burst T 0 Time resolution detector & electronics Neutron transport in target - moderator Neutron transport in detector T s t t t d
53 Resolution: detector & electronics (T s ) Mostly supposed to be normal (Gaussian) distributed Strongly depends on detector type e.g. C 6 D 6 liquid scintillator < 1 ns Li-glass scintillator < 1ns Frisch-grid ionisation chamber Ge-detector (with RTP) 10 ns 0 ns Mostly response of (T s - T 0 ) lumped in one normal distribution
54 Time-of-flight technique: experimental resolution t = (T s T 0 ) + t o ( t t +t d ) t Initial burst T 0 Time resolution detector & electronics Neutron transport in target - moderator Neutron transport in detector T s t t t d
55 R(t t,e) Resolution: Probability distribution of t t GELINA x 10-3 x 10 - x ev 1 - ev 1 - kev kev Response function Time, t t / s Flaska et al., NIM A 531, 394 (004)
56 Equivalent distance : L t = v t t dl P(t t,e n) P'(L t(t t ), E n) dt t t
57 Probability desinsity Equivalent distance : L t = v t t dl P(t t,e n) P'(L t(t t ), E n) dt t t ev ev ev ev ev ev cm 1-5 ev Distance / cm
58 Probability desinsity TOF response function R(L t,e n ) ev ev ev ev ev ev cm 1-5 ev Distance / cm
59 Probability desinsity Probability desinsity TOF response function R(L t,e n ) ev ev ev ev ev ev ev ev ev ev ev ev ev cm Distance / cm Distance / cm
60 Eq. Distance / cm Width / cm TOF response function: characteristics Average eq. distance Target equivalent distance Moderated beam Flight path : 0 o Most probable Average Neutron Energy / ev Resolution function Target equivalent distance Moderated beam Flight path : 0 o FWHM.35 Neutron Energy / ev
61 Neutron production & transport: analytical Different components (analytical approach) Neutron production Exponential decay Neutron moderation - distribution + Storage term (Ikeda & Carpenter) Cole and Windsor function (applied at JPARC) Neutron emission : direction flight path with respect to moderator
62 Probability Density Neutron production & transport: analytical 10 0 Monte Carlo REFIT (adjusted to exp.) Analytical approximation 10-1 Below 0.5 ev : + storage 10 - Between 0.5 ev and 1000 ev: dominated by due to moderation 10-3 process and almost independent of E n Above 1000 kev : more complex Delay distance / m Equivalent Distance / m
63 R(t t,e) P(t t, E) : photonuclear.0 GELINA 40 m E n = 35 kev (L / t m ) / (m/s)
64 R(t t,e) P(t t, E) : photonuclear GELINA ORNL 40 m 40 m E n = 35 kev (L / t m ) / (m/s)
65 R(t t,e) P(t t, E) : photonuclear spallation reactions GELINA ORNL ntof 40 m 40 m 180 m E n = 35 kev Dimensions : cm 3 Pure Lead : 4 t H O moderator : 5 cm Al-window : 1.6 mm Al-container : 140 l (L / t m ) / (m/s) Resolution : L GELINA : cm ORELA : cm ntof : 1 cm
66 R(t t,e) R(t t,e) P(t t, E) : photonuclear spallation reactions GELINA 3 m E n = 35 kev GELINA ORNL ntof 40 m 40 m 180 m E n = 35 kev (L / t m ) / (m/s) (L / t m ) / (m/s) Resolution GELINA ORELA ntof : L : cm : cm : 1 cm
67 R(t t,e) R(t t,e) P(t t, E) : photonuclear spallation reactions GELINA ISIS 3 m 3 m E n = 35 kev GELINA ORNL ntof 40 m 40 m 180 m E n = 35 kev (L / t m ) / (m/s) (L / t m ) / (m/s) Resolution GELINA ORELA ntof : L : cm : cm : 1 cm
68 R(t t,e) R(t t,e) P(t t, E) : photonuclear spallation reactions GELINA ISIS JPARC 3 m 3 m 3 m E n = 35 kev GELINA ORNL ntof 40 m 40 m 180 m E n = 35 kev (L / t m ) / (m/s) (L / t m ) / (m/s) Resolution GELINA ORELA ntof : L : cm : cm : 1 cm
69 R(t t,e) R(t t,e) P(t t, E) : photonuclear spallation reactions GELINA ISIS JPARC 3 m 3 m 3 m E n = 35 kev GELINA ORNL ntof 40 m 40 m 180 m E n = 35 kev (L / t m ) / (m/s) Resolution : L ISIS (INES) : 5 cm J-PARC (MLF/ANNRI) : 13 cm Strongly depend on target/moderator configuration (coupled/decoupled) (L / t m ) / (m/s) Resolution : L GELINA : cm ORELA : cm ntof : 1 cm
70 TOF response matrix
71 Neutron production & transport Photonuclear GELINA Flaska et al. NIMA 531 (004) 394 Ene et al., NIM A 618, 54 (010) ORELA Coceva et al., NIM 1, 459 (1983) RPI Overberg et al., NIM A 438, 53 (1999) Spallation source ntof Gunsing et al., NIM B 61, 95 (007) J-PARC Hasemi et al., NIM A 773 (015) 137
72 Time-of-flight technique: experimental resolution t = (T s T 0 ) + t o ( t t +t d ) t Initial burst T 0 Time resolution detector & electronics Neutron transport in target - moderator Neutron transport in detector T s t t t d
73 R(L d,e) Li-glass scintillator : response function 6 Li(n,t)a Scintillator + PMT E n =10 ev MCNP Equivalent distance, L d / cm
74 R(L d,e) Li-glass scintillator : response function 6 Li(n,t)a Scintillator + PMT E n =10 ev MCNP Analytical (REFIT) Equivalent distance, L d / cm
75 R(L d,e) R(L d,e) Li-glass scintillator : response function 1.0 E n =100 ev 1.0 E n =10 ev MCNP Analytical (REFIT) MCNP Analytical (REFIT) Equivalent distance, L d / cm Equivalent distance, L d / cm
76 Time-of-flight technique v v t t L L E E (1 ) v v
77 Time-of-flight technique v v t t L L 1 L (vt) L E E (1 ) v v
78 Time-of-flight technique Components: Initial burst T 0 Time resolution detector & electronics T s Neutron transport in target - moderator t t L t (equivalent length = v t t ) Neutron transport in detector t d L d (equivalent length = v t d ) with (T 0, T s, L t, L d ) almost independent of neutron energy (velocity) v v 1 L t t (v T L L 1 L (vt) 0 ) (v Ts ) L t L d L L X E E (1 ) v v neglibible REFIT: numerical and analytical response functions + combination
79 E / E TOF-resolution : different components v v 1 L (v T ) (v Ts ) L t L d L = 30 m " L " E E (1 ) v v 10-3 L = cm T = T = 100 ns T = 10 ns T = 1 ns L = cm L = cm L = 0 cm L = cm Neutron Energy energy / kev/ ev
80 Yield Experimental observable FWHM D with - Total resonance width R x FWHM = Exp. Analytical (REFIT) MCNP R = D = = 43 ev 4 ev 15 ev ev - R Experimental resolution D Doppler broadening Neutron energy / ev
81 Doppler broadening (T,v) 1 v v V ( v V )P(V) dv v : neutron velocity V : target velocity P(V) : target velocity distribution : nuclear (microscopic) cross section : Doppler broadened (microscopic) cross section T : effective target temperature
82 Doppler broadened cross sections tot / b x U + n T = 0 K T = 300 K T = 1000 K (T,v) 1 v (E) de' S(E,E') (E' ) (E) D D v V ( v V )P(V) dv 1 m de' e 4 Ek X FWHM B /m E' E D T n ln D E' E (E') Neutron energy / ev
83 Yield Theoretical capture yield Fe 1.15 kev resonance D = R = 0 Area density : at / barn Y tot (1 e n tot ) Neutron Energy / ev
84 Yield + Doppler Fe 1.15 kev resonance Area density : at / barn D = R = 0 D (kt = 5 mev) Y tot (1 e n tot (E) de' S(E') (E E' ) ) (E) D 1 de' e E' E D E' E (E') D 4 Ek m X B T /m n Neutron Energy / ev FWHM ln D
85 Yield + Doppler + Response Fe 1.15 kev resonance Area density : at / barn D = R = 0 D (kt = 5 mev) Y tot (1 e n tot (E) de' S(E') (E E' ) ) R for L = 60 m Y exp R(t,E)Y (E)dE R(t,E)dE L = 60 m E E L L t t Neutron Energy / ev
86 Yield + Doppler + Response Fe 1.15 kev resonance Area density : at / barn D = R = 0 D (kt = 5 mev) Y tot (1 e n tot (E) de' S(E') (E E' ) ) R for L = 60 m + R for L = 30 m Y exp R(t,E)Y (E)dE R(t,E)dE L = 60 m L = 30 m E E L L t t Neutron Energy / ev
87 Yield + Doppler + Response Fe 1.15 kev resonance Area density : at / barn D = R = 0 D (kt = 5 mev) Y tot (1 e n tot (E) de' S(E') (E E' ) ) R for L = 60 m + R for L = 30 m + R for L = 1.5 m Y exp R(t,E)Y (E)dE R(t,E)dE L = 60 m L = 30 m L = 1.5 m E E L L t t Neutron Energy / ev
88 Yield 197 Au(n,) at L = 1 m E E L L t t D 4 Ek m X B T /m n FWHM ln D m R ~ 00 mev ~ 10 mev D ~ 940 mev Neutron Energy (ev)
89 Yield 197 Au(n,) at L = 1 m and 30 m E E L L t t D 4 Ek m X B T /m n FWHM ln D m R ~ 00 mev m R ~ 840 mev ~ 10 mev D ~ 940 mev Neutron Energy (ev)
90 Yield Yield 197 Au(n,) at L = 1 m and 30 m E E L L t t D 4 Ek m X B T /m n FWHM ln D m R ~ 00 mev m R ~ 00 mev m R ~ 80 mev m R ~ 840 mev ~ 10 mev D ~ 300 mev ~ 10 mev D ~ 940 mev Neutron Energy (ev) Neutron Energy (ev)
91 Yield Experimental observable when < R or D FWHM D Ofter dominated by R or D with - Total resonance width R x FWHM = Exp. Analytical (REFIT) MCNP R = D = = 43 ev 4 ev 15 ev ev - R Experimental resolution D Doppler broadening effective experimental observable is resonance area Neutron energy / ev
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