Neutron-induced cross-section measurements by
activation technique and gamma-ray
spectrometry in the energy range up to 20 MeV.
Compilation of experimental nuclear reaction
data in EXFOR database
Valentina Semkova
Institute for Nuclear Research and Nuclear
Energy, Bulgarian Academy of Sciences, Sofia,
Bulgaria
Content
Neutron-induced activation reaction cross section measurements
Neutron source characterization
Irradiation geometry
HPGe detector characterization
Sample composition
Cross section uncertainties
True coincidence summing correction calculations and uncertainty
calculation
EXFOR compilation of experimental nuclear reaction data
JINR, DUBNA 6 November 2019
Neutrinics calculations Boltzmann: Neutron transport
Bateman: Nuclide evolution
1. Neutron flux distribution in space and
energy (slowing down through elastic
scattering and secondary particle emission
(n,nʹg), (n,xn))
2. Radioactivity inventory based on
irradiation history (low activation
materials required).
3. Sensitivity (SR=(∂R/∂σ)(σ/R)) and
uncertainty (including correlations) analysis
required to provide adequate estimation for
the uncertainty of the integral
characteristics.
4. Nuclear data evaluations based on
experimental data and model calculations
Activation cross sections and uncertainty propagation
• A is the number of counts, c flux in1i 1 1 exp ti
• n is the number of atoms in the exp texp n it
target per area, clow 1 iEm0ax breakupi E . fi E dE
• e is the detector efficiency
• I is the gamma ray intensity E max i E . f i E dE
• λ is the decay constant E 0
• ti, tc, tm, irradiation, cooling and
cabs 1 1 exp x
measurement time x
Uncertainty propagation
Linear function
The general formalism of propagation of the variance and the covariance of the
parameter xk to those of yi is based on up to first order Taylor expansion of yi around
the expectation value xk0 of xk.
Neutron source characterization I
Neutron production in the 2-3 MeV and 13.5-14.8 energy ranges using D-D
and D-T at Ed~kev
high intensity; low background; neutron emission in 4π; limited energy range, kinematics
well known, Zr/Nb ration method used to verify neutron energy at sample position.
0 degrees 90 degrees
Fluence (n/(cm2 MeV s) 7,0E+07
6,0E+07
5,0E+07 14,5 15 15,5
4,0E+07
3,0E+07 Neutron energy (MeV)
2,0E+07
1,0E+07
0,0E+00
14
Neutron source characterization II
Neutron production in the 13.8 - 20.5 MeV energy range from D-T
reactions at Ed=1 to 4 MeV (Van de Graaff accelerator)
wider energy range; neutron emission in 4π; quasi-monoenergetic neutrons
background of low-energy neutron distribution; relatively low intensity
o TOF spectra measurement
•Liquid scintillator (NE213):
•Pulsed VdG: 1.5 ns fwhm, long tails, 400 ns rep. period
•3 m flight-path
•Collimator to avoid scattered neutron contributions
o Reaction rate measurements for the
following dosimetry reactions:115In(n,n)115mIn,
58Ni(n,p)58m+gNi, 56Fe(n,p)56Mn, 27Al(n,p)27Mg,
27Al(n,)24Na and 93Nb(n,2n)92mNb
o Adjustment of ′k for 6 energy intervals by
GLSM bases on standard reactions group cross
sections and measured reaction rates
Neutron source characterization III
Neutron production in the 4 - 13 MeV energy range from D-D reactions
at Ed=4 to 11 MeV (Cyclotron accelerator)
Neutron emission predominantly in forward direction; quasi-monoenergetic
neutrons high background of low-energy neutron distribution.
Fig. 1. Evaluated cross sections and the 0-deg neutron
spectrum of the D(d,n)3He reaction at 9.02 MeV.
Cabral et al., Nucl. Sci. Eng. 106, 308-317 (1990).
Neutron source characterization IV
Deuteron beam on thick 9Be target: very high intensity; broad energy
distribution, respectively spectrum average cross sections
Irradiation geometry
T1/2 ≥ min 3 s ≤ T1/2
T1/2=15.663 s
:
T1/2=6.21 s
Samples characteristics: natural and enriched
(n,γ) (n,3n)
(n,2n)
(n,p) (n,n+p)
HPGe detector characterisation
The Monte Carlo simulation of the
detector response allows taking into
account the detailed characteristics of
the detector and samples (complex
shape, sample matrix, γ-ray self-
attenuation, volume activity
distribution, coincidence summing
effects, etc.
Application of MC calculated detector efficiency
Total efficiency (%) 30
25
20
15
10
5 W sample 0.25 mm thick
Point soirce
0
0 200 400 600 800 1000 1200 1400
Gamma-ray energy (keV)
Threshold
(n,t) 6.4 MeV
(n,nd) 19.3 MeV
(n,2np) 21.6 MeV
Decay constant:
T1/2 15.97 d
Eg 983.525 keV
Ig 99.89(4) %
Sample size:
ø 30 x 5 mm
Interference: No
Counting rate (cps)241Am(n,2n)240Am cross section measurements
4
3 988 keV
988 keV
889 keV
889 keV
2
1
0
0 20 40 60 80 100 120 140 160 180
Cooling time (h)
Cross section uncertainty calculations
not correlated
correlated
Isomeric cross section measurement by analysis of
complex decay curve
n p m p p m
g m m g
Ng
tc g m 1 egT egtc 1 emT emtc
g
Ng tc
~ Ae Begtc mtc 70
A 58gCo decay curve
B 68
m g m g 1 1 egT
g m 1 emT 66
Activity (cps) 5+ 24.889 9.15 h
c 64
1 emT IT
1 egT 62 2+ 0 70.8 d
EC 58Co
60
IR m Measured
Fitted
m g
m g 1 58 58Fe
g
c A B 1 0 5 10 15 20 25 30
Cooling time (h)
True coincidence summing (TCS) correction
TCS uncertainty propagation
Cs-134 b- decay
EXFOR: scope of compilation
total
neutrons
charged particles
photons
Incident energy range up to 1 GeV
Quantities:
Cross sections CS (51%); Partial differential with respect to angle DAP (19.4%)
Differential data with respect to angle DA (19.3%); Resonance parameters RP (8.89);
Partial cross section data CSP (8.53%); Polarisation data POL (5.15%);
Fission product yields FY (5.03%); Differential data with respect to angle and energy DAE (4.78%); Fission
neutron quantities MDQ (2.27%); Gamma spectra SP (2.14);
Resonance integrals RI (2.08); Differential data with respect to energy DE (1.74%);
Thick target yields TT (1.65%) etc.
Reaction fields:
SF1. Target Nucleus
SF2. Incident particle
SF3. Process
SF4. Reaction Product
Data type fields:
SF5. Branch
(partial reactions)
SF6. Parameter
SF7. Particle considered
SF8. Modifier
(rel. data; fitting coeffi.)
(SF1(SF2,SF3)SF4,SF5,SF6,SF7,SF8,SF9)
Summary
Activation data are needed in many fields of science and
applications.
All factors/corrections influencing the particular
interaction needs to be carefully studied in order to obtain
accurate data.
Uncertainty analysis including covariance data have to
improve precision.
The new experimental data improve the knowledge of the
excitation functions the parameterization model calculations.