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9.019000+3 1.883500+1 0 0 2 2
0.000000+0 0.000000+0 0 0 0 6
1.000000+0 2.000000+7 8 0 10 31
0.000000+0 0.000000+0 0 0 216 1
9-F - 19 CNDC,ORNL EVAL-JUN90 Z.X.ZHAO,C.Y.FU,D.C.LARSON
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 925
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: Pre-ENDF/B-VII **
** **
******************************************************************
****************************************************************
Reevaluation of the F-19 resonance parameters in the energy range
up 1 MeV done by L. C. Leal, H. Derrien (and) N. M. Greene (ORNL)
Reevalaution of the F-19 cross sections up to 1 MeV. Resoanance
parameters were obtained with the computer code SAMMY by
fitting three transmission measurements of Larson with thicknesses
of 0.13093 at/b, 0.016886 at/b, and 0.024184 at/b, respectively,
measured on the 80-m flight path at the Oak Ridge Linear (ORELA)
Accelerator, one capture cross section of Guber measure up to
700 keV and one inelastic cross section measumrement of Broder up
to 1 MeV. The result of the resonance analysis is a set of
resonance parameters containing thirty-five resonances which one
resonance is negative to account for the bound levels and three
lies above the cutoff energy of 1 MeV to account for the effect
for the truncated resonances above 1 MeV. The 31 resonances in the
the energy range up to 1 MeV are 2 s-wave, 5 p-wave, 17 d-wave,
and 7 f-wave. In the energy up 1 MeV F-19 has inelastic channels
starting at the energies 109.9 keV with spin 1/2- and 197.2 keV
with spin 5/2+. These two channels were included in the Reich-
Moore evalaution with SAMMY. At the present time, cross section
processing codes do not have capability to include inelastic
channels. Therefore, the evaluation presented here is the
pointwise cross section processed with SAMMY. The resonance
parameters evaluation will be released as soon as the processing
codes are able to process Reich-Moore parameters with inelastic
channels.
The cross sections at 300 K at thermal are the following:
Total 3.7496 b
Scatting 3.7400 b
Capture 9.5784-3 b
******************************************************************
ENDF/B-VI MOD 2 Revision (S.C.Frankle, R.C.Reedy, P.G.Young,
J. Campbell, R. Little (LANL) August, 2001
The secondary gamma-ray spectrum for radiative capture (MF 12,
MT 102) has been updated for new experimental data at incident
neutron energies up to 200 keV. The Q-value for radiative capture
was also updated in File 3. Details of these changes are
described in Frankle et al. [Fr01].
Note that the radiative capture data were changed from pure
continuum data in MF=6, MT=102, to discrete plus continuum data
in MF=12,14,15, MT=102. The continuum spectra above 200 keV are
unchanged from MOD 1, but the yields were modified slightly in
MF=12,MT102 for energy conservation. The thermal neutron photon
production spectrum is comprised of 168 discrete photons.
Two negative probability values (MF=6 MT=28 and MF=6 MT=107)
were changed (update of August 2001):
-5.08530e-12 -> 5.08530e-12 and -1.3263e-7 -> 1.3263e-7
****************************************************************
ENDF/B-VI MOD 1 Evaluation, June 1990, Z.X.Zhao, C.Y. Fu,
D.C. Larson (ORNL)
This evaluation is based on measured data available on csisrs
and a theoretical calculation using the TNG statistical and
precompound theory code [SH86,FU88].
FILE 2. RESONANCE PARAMETERS
SECTION 151 Only scattering length [KO79] is given.
FILE 3. NEUTRON CROSS SECTION
SECTION 1. TOTAL INTERACTION
1.0E-05 to 10 eV: Sum of free atom scattering cross
section and the capture cross section.
10 Ev to 2.0 MeV: Calculated from a set of resonance
parameters which were adjusted to fit the high
resolution measured total cross sections [LA76] by
using the SAMMY multi-level R-matrix analysis code [LA87].
2.0 MeV to 20 MeV: The values of ENDF/B-V are used.
SECTION 2. ELASTIC SCATTERING
Obtained by subtracting the non-elastic cross section
from total cross section.
SECTION 3. NON-ELASTIC SCATTERING
Obtained by setting MT3 =
MT4+MT16+MT22+MT28+MT102+MT103+MT104+MT105+MT107.
SECTION 4. TOTAL INELASTIC SCATTERING
Obtained by summing MT=51-71 and 91.
SECTION 16. (N,2N) REACTION
Calculated by TNG code.
SECTION 22. (N,NA)+(N,AN) REACTION
Calculated by TNG code.
SECTION 28. (N,NP)+N,PN) REACTION
Calculated by TNG code.
SECTIONS 51 AND 52. INELASTIC SCATTERING FOR FIRST AND SECOND
LEVELS
Obtained by CS(EX)/MG(TNG), where CS(EX) denotes measured
110 keV and 197 keV gamma-ray production cross section
[MO74], MG(TNG) are multiplicities for 110 and 197 keV
calculated by TNG.
SECTIONS 53 - 71. INELASTIC SCATTERING FOR OTHER LEVELS
Calculated by TNG and DWUCK [KU72].
SECTION 91. CONTINUUM INELASTIC SCATTERING
Calculated by TNG.
SECTION 102. (N,GAMMA) REACTION
1.0E-05 eV to 2.0 MeV: Calculated by SAMMY code using a set
of resonance parameters used in the calculation for total
cross sections, but gamma-widths were adjusted to fit the
measured data of Macklin [MA63] and Gabbard [GA59].
Above 2.0 MeV, capture cross sections are very small so 1/E
is used to extrapolate to 20 MeV.
SECTION 103. (N,P) REACTION
For energies < 8.0 MeV, ENDF/B-V remains unchanged.
Above 8.0 MeV: Calculated by TNG code.
SECTION 104. (N,D) REACTION
Calculated from systematics [ZH88].
The excitation function was normalized to 22 mb given by
integrating early angular distribution data of Fazio [FA68],
and [RE68] at 14 MeV.
SECTION 105. (N,T) REACTION
Calculated from systematics [ZH88]. The excitation function
was normalized to spectrum averaged measured data of Qaim
[QA78].
SECTION 107. (N,A) REACTION
For energies < 9.0 MeV, ENDF/B-V remains unchanged.
Above 9.0 MeV, calculated by TNG code.
FILE 4. ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
SECTION 2. ELASTIC SCATTERING
The Legendre coefficients are calculated by the GENOA
optical model code [PE67] with compound cross sections
and Legendre coefficients calculated by TNG as input.
Before calculation, optical model parameters were adjusted
to fit measured angular distributions of Baba [BA85] and
Clarke [CL70]. Same optical model parameters were used in
TNG, DWUCK and GENOA calculations.
SECTIONS 51-71. INELASTIC SCATTERING
The cross sections CS(D), Legendre coefficients FL(D)
contributed from direct interaction were calculated by
DWUCK and CS(S), FL(S) are from statistical model by
TNG, using
CS(D)*FL(D) + CS(S)*FL(S)
FL = ------------------------------
CS(D) + CS(S)
FILE 6. DOUBLE DIFFERENTIAL CROSS SECTIONS(DDCS)
The cross sections for all sections were obtained based on
TNG calculations for the first outgoing neutrons only. For
the second outgoing neutrons and both the first and second
outgoing charged particles, the angular distributions were
assumed isotropic. Recoil spectra are generated as the
calculated particle spectra were inverted to the laboratory
system.
FILE 8. RADIOACTIVE DECAY DATA
FILE 9. MULTIPLICITIES FOR PRODUCTION OF RADIOACTIVE NUCLIDES
FILE 12. TRANSITION PROBABILITY ARRAYS
SECTIONS 51-71.
Based on [AJ87].
FILE 14. PHOTON ANGULAR DISTRIBUTION
SECTIONS 51-71. INELASTIC SCATTERING
Isotropic.
FILE 33. UNCERTANTIES OF FILE 3
SECTIONS 1,51,52,102,103 AND 107:
Same as ENDF/B-V but supplemented a sub-subsection of LB=8
for every section.
SECTION 2 AND 3:
Using "NC-TYPE" sub-subsection for these two derived cross
sections.
SECTIONS 4,16,22 AND 28:
Calculated from a covariance matrix of theoretical
parameters (several most sensitive parameters were chosen
as follows: energy level density parameters for 19F, 19O
and 16N; optical model parameters for 19F: V0 and W for
real and imaginary well depths, RU and RW for the radius
of real and imaginary potential). The covariance matrix
for theoretical parameters was estimated based on scatter
of measured data available around theoretical values and
systematic error of measured data. A sub-subsection of LB=8
is also given for every section.
SECTIONS 104 AND 105:
Calculated from covariance matrix of systematics parameters
[ZH88]. A sub-subsection of LB=8 is also given for every
section.
****************************************************************
REFERENCES
[AJ88] F. Ajzenberg-Selove, A475, 1 (1987)
[BA85] M. Baba et al., Proc. Conf. on Nucl.Data for Basic
and Applied Science, Santa Fe, May 1985
[CL70] W. Clarke et al., Nucl.Phys., A147, 174 and 1970)
[CS90] CSISRS/EXFOR data.
[FA68] M. Fazio et al., Nucl.Phys., A111, 255
[Fr01] S.C. Frankle, R.C. Reedy, and P.G. Young, Los Alamos
National Laboratory Report, LA-13812 (2001).
[FU88] C.Y. Fu, Nucl.Sci.Eng., 100, 61 (1988)
[GA59] F. Gabbard et al., Phys.Rev., 114, 201 (1959)
[KO79] L. Koester et al., Z.Physik, A292, 95 (1979)
[KU72] P.D. Kunz, "Distored Wave Code DWUCK72", University of
Colorado (1972)
[LA76] D.C.Larson et al., Oak Ridge report ORNL-TM-5612 (1976)
[LA87] N.M. Larson, Oak Ridge report ORNL/TM-9179 (1987)
[MA63] R.L. Macklin et al., Phys.Rev., C7, 1766 (1963)
[M074] G.L. Morgan and J.K. Dickens, Oak Ridge report ORNL/TM-4823
(1974)
[PE67] F.G. Perey, computer code GENOA, ORNL, unpublished (1967)
[QA78] S.M. Qaim et al., Nucl.Phys., A295, 150 (1978)
[SH86] K. Shibata and C.Y. Fu, Oak Ridge report ORNL/TM-10093
(1986)
[ZH88] Z. Zhao and Z. Zhou, Nucl.Sci.Eng., 99, 367 (1988)
************************ C O N T E N T S ***********************
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