6-C - 0
6-C - 0 JAERI EVAL-AUG83 K.SHIBATA
JAERI-M 83-221 DIST-MAR02 REV3-SEP00 20000911
----JENDL-3.3 MATERIAL 600
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
83-08 Newly evaluated by k.shibata
Details of the evaluation are given in ref./1/.
84-07 Data of mf=4 mt=91 were revised.
Comment was also modified.
85-02 Data of mt=2, 3, 4, 53 of mf=3 were revised above 10.45
MeV. Angular distributions for mt=52, 53 were also
revised.
88-07 Data of mt=1, 3, 4, 52 of mf=3 were revised above 8.3 MeV.
93-12 JENDL-3.2
Inelastic scattering and capture cross sections were
reevaluated by K. Shibata (jaeri).
Pseudo levels were generated to reproduce vailable ddx
data.
The total cross section was replaced with the R-matrix
calculation done in ref./1/.
All data were compiled by K. Shibata.
***** modified parts for JENDL-3.2 ********************
(3,1) R-matrix calcultion/1/.
(3,2) Total - noelastic
(3,3) Sum of partial reaction cross sections
(3,4) Sum of (3,51-91)
(3,51) Modified by considering experimental data.
(3,53),(3,58)
Coupled-channel statistical model cal.
(3,52),(3,54-57),(3,59-75)
Pseudo levels.
(3,91) 4-body breakup.
(3,102) Modified by taking account of p-wave capture.
(4,51-91)
(5,91) 4-body phase space
(12,102) Experimental data for 20-200 keV.
********************************************************
96-01 Adopted in JENDL fusion file
96-08 Modification for FENDL-2 (S. Chiba)
(3,2) below 4.8 MeV and (4,2) were taken from
FENDL-1 (=ENDF/B-VI) as requested by IAEA-AGM
(Karlsruhe, June 1996).
00-09 JENDL-3.3 is based on JENDL/F-99.
****** modified parts for JENDL-3.3 *******************
(1,451) Modified
(3,3) Deleted
(3,251) Deleted
(5,91) Distributions at threshold were modified.
Interpolation was changed to 22.
(14,102) NK=10
The data should be regarded as elemental data.
********************************************************
mf=1 General information
mt=451 Descriptive data
mf=2 Resonance parameters
mt=151 Scattering radius only.
mf=3 Cross sections
Calculated 2200m/s cross sections and res. integrals
2200m/s (b) res.integ. (b)
total 4.750 -
elastic 4.746 -
capture 0.0035 0.0018
mt=1 Sig-t
Below 4.8 MeV, the cross sections were obtained to be
the sum of non-elastic and elastic for FENDL-2.
Above 4.8 MeV, based on the measurements /8/-/10/.
mt=2 Sig-el
Below 10 eV, sig-el = 4.746 barns.
Above 10 eV, the cross section was obtained by subtracting
the reaction cross section from the total cross section.
**********************************************************
The cross sections below 4.8 MeV were replaced with those
given in FENDL-1.
**********************************************************
mt=4 Total inelastic
Sum of mt=51-75 and 91.
mt=51 Sig-in 4.44 MeV level
Based on the experimental data /11,27,30,31/.
mt=53,58 Sig-in 7.65 MeV (0+), 9.64 MeV (3-) levels
The cross sections were obtained from coupled-channel
and statistical model calculations.
mt=52,54-57,59-75 Pseudo levels (n,n'3alpha)
Pseudo levels with an interval of 500 keV were made in
order to simulate sequential (n,n') decay (evaporation
shape) and 3-body breakup (phase space) leading to
(n,n'3alpha). The sum of the cross sections for pseudo
levels and mt=91 is consistent with the measurement/12/
except around the threshold energy where the calculated
cross sections were enhanced.
mt=91 (n,n'3alpha)
Contribution from 4-body breakup. The cross section
was adjusted so that the calculated spectrum could give
a good fit to experimental data at 14 MeV.
Total (n,n')3a cross section is the sum of mt=52-75
and 91.
mt=102 Capture
Below 100 eV, 1/v curve.
Between 100 eV and 5 MeV, s-wave plus p-wave capture
by considering the data of Igashira/32/.
Above 5 MeV, the inverse reaction data of Cook /13/ were
added.
mt=103 (n,p)
Based on the measurement of Rimmer and Fisher /14/.
mt=104 (n,d)
Calculated with DWBA.
mt=107 (n,a)
Based on the experimental data /15/-/23/.
mf=4 Angular distributions of secondary neutrons
mt=2
Taken from FENDL-1.
mt=51
Based on the experimental data /24/-/28//33/.
mt=53, 58
Based on the experimental data /33/.
mt=52,54-57,59-75
Isotropic in cm.
mt=91
Isotropic distributions in lab.
mf=5 Energy distribution of secondary neutrons
mt=91
4-body phase space.
mf=12 Photon-production multiplicities
mt=51 (n,n')gamma
m=1.0
mt=102 (n,gamma)
Based on the measurement of Spilling et al./29/ and
of Igashira /32/.
mf=14 Photon angular distributions
mt=51
Based on the experimental data of Morgan et al./11/.
mt=102
Assumed to be isotropic.
References
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