26-Fe- 56
26-Fe- 56 JNDC EVAL-MAR87 S.IIJIMA,H.YAMAKOSHI
DIST-MAY10 20100316
----JENDL-4.0 MATERIAL 2631
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 Evaluation was performed for JENDL-3.
87-05 Compiled by K.Shibata (jaeri).
******JENDL-3.2 *************************************************
93-07 Modfifcation was made for (3,51-55),(3,59),(3,91).
Files 4 and 5 for mt=16,22,28,19 were obtained from the
file-6 of the JENDL Fusion File /1/.
Data for (3,4) were reconstructed.
(3,2) = total - nonelastic
93-11 Data for (12,102) and (15,102) were reevaluated by
S. Igarasi (nedac).
94-03 As for (3,2) and (3,107), small cross-section values
were replaced with 0.0.
Data were compiled by K. Shibata (jaeri).
*****************************************************************
2000-04 Re-evaluated and compiled by K.Shibata (jaeri) for
JENDL-3.3.
**************** modified parts for JENDL-3.3 ********************
(1,451) Modified.
(2,151) Taken from Froehner's evaluation for JEF-2.
(3,1) Re-evaluted.
(3,2) Re-calculated.
(3,16) Re-evaluated.
(3,102) Pre-equilibrium capture was considered above 5 MeV.
(3,251) Deleted.
(4,2) Re-evaluated. Transformation matrix deleted.
(4,16),(4,22),(4,28),(4,91) Deleted.
(5,16),(5,22),(5,28),(5,91) Deleted.
(6,16),(6,22),(6,28),(6,91) Taken from JENDL/F-99 /1/.
(12,102),(15,102) Between 27.5 and 570 keV,
based on experimental data.
******************************************************************
2002-01 Covariances were taken from JENDL-3.2 covariance file
except for MF/MT=3/1.
2008-10 Revised for JENDL-4 by K. Shibata (jaea)
**************** modified parts for JENDL-4 **********************
(1,451) Comments modified
(3,1) Re-calculated
(3,2) Re-calculated
(3,4) Re-calculated
(3,51) Revised Hauser-Feshbach + coupled-channel calculations
above 2.1 MeV
(3,52) Revised Hauser-Feshbach + coupled-channel calculations
in the whole energy range
(3,53) Revised Hauser-Feshbach + coupled-channel calculations
in the whole energy range
(4, 2) Revised by taking account of experimental data and
model calculations
******************************************************************
2010-03 Covariances were partly revised.
******************************************************************
(33,1),(33,51),(33,53),(33,54),(33,55),(33,56),(33,58),(33,61),
(33,62),(33,63),(33,64),(33,65),(33,67),(33,73),(33,75),(33,77),
(33,91) revised
******************************************************************
mf=1 General information
mt=451 Descriptive data and dictionary
mf=2 Resonance parameters
mt=151 Resolved resonances
Resonance region = 1.0e-5 eV to 850.0 keV
The Reich-Moore formula was used. Paremeters were obtained
from Froehner's evaluation for JEF-2 /2/.
calculated 2200-m/s cross sections and res. integrals.
2200-m/s res. integ.
elastic 12.08 b -
capture 2.590 b 1.348 b
total 14.67 b -
mf=3 Neutron cross sections
Below 850 keV, background cross sections were given
for the elastic and capture cross sections.
Above 850 keV, cross sections were evaluated as follows.
mt=1 Total
Between 850 keV and 7 MeV, fine structure measured by
Berthold et al./3/ was followd. Above 7 MeV, the
cross sections were obtained from a least-squares fit to
the measurements /3,4,5/.
The contributions from Fe-54, 57, 58 were subtracted from
the measured cross sections of elemental iron.
mt=2 Elastic scattering
Given as total minus nonelastic cross sections.
mt=16,22,28 (n,2n),(n,n'a),(n,n'p)
Calculated with gnash /6/.
For JENDL-3.3, the (n,2n) cross section was modified /7/
by considering the tng /8/ calculation.
mt=4,51-77,91 Inelastic scattering
The casthy and gnash calculations were adopted for
neutron energies below and above 7 MeV, respectively.
The direct-process component was considered for mt=
51,52,53,54,77 by the c.c. theory.
Spherical optical model calculation was made by using
casthy code /9/. parameters are as follows:
V = 46.0-0.25*E , r0=1.286, a0=0.620
Ws = 14.0-0.20*E , rs=1.390, as=0.700
Vso= 6.0 , rso=1.07, aso=0.620
(energies in MeV, lengths in fm).
The level scheme is given as follows:
no. energy(MeV) spin-parity
g.s. 0.0 0 +
1. 0.8468 2 +
2. 2.0851 4 +
3. 2.6576 2 +
4. 2.9417 0 +
5. 2.9600 2 +
6. 3.1200 1 +
7. 3.1229 4 +
8. 3.3702 2 +
9. 3.3884 6 +
10. 3.4454 3 +
11. 3.4493 1 +
12. 3.6009 2 +
13. 3.6019 2 +
14. 3.6070 0 +
15. 3.7480 2 +
16. 3.7558 6 +
17. 3.8320 2 +
18. 3.8565 3 +
19. 4.0940 3 +
20. 4.1003 3 +
21. 4.1200 4 +
22. 4.2982 4 +
23. 4.3020 0 +
24. 4.3950 3 +
25. 4.4010 2 +
26. 4.4584 3 +
27. 4.5100 3 -
Continuum levels were assumed above 4.701 MeV.
***** JENDL-3.2 *******************************************
For mf/mt=3/51 between threshold and 2.1 MeV, evaluated
data were obtained from high resolution data of Voss et
al. /10/ by taking account of gamma-ray angular distri-
butions /11/.
The cross sections for mt=54,91 were replaced with those
contained in the JENDL Fusion File.
As for mt=59, a point at 11.7 MeV was deleted.
Furthermore, the cross sections for mt=52-55 were modi-
fied around threshold by considering the measurements
/12,13/.
***********************************************************
***** JENDL-4 *********************************************
Fort mt=51,52,53, Hauser-Feshbach + coupled-channel
calculations were performed with POD /20/ and OPTMAN /21/
codes by using the neutron potentials obtained by Kunieda
et al./22/
As for mt=51, experimentally determined resonance cross
sections were kept from the threhold to 2.1 MeV.
***********************************************************
mt=102 Capture
Below 850 keV, background is given. Above 850 keV,
For JENDL-3.3, the pre-equilibrium capture process was
taken into account /7/.
mt=103 (n,p)
Below 7 MeV, based on the data of Smith and Meadows/14/.
7 - 13 MeV, taken from JENDL-2.
13 - 16 MeV, based on the data of Ikeda et al./15/
16 - 20 MeV, taken from JENDL-2.
mt=107 (n,alpha)
Based on experimental data.
mt=203 Proton production
Sum of mt=28 and 103.
mt=207 Alpha production
Sum of mt=22 and 107.
mf=4 Angular distributions of secondary neutrons
mt=2,51-77
Optical and statistical-model calculations were adopted.
the c.c. calculations were added to the levels of mt=51,52,
53,54,77.
For JENDL-3.3, above 10 MeV, mt=2 data were replaced with
the optical model calculations using the neutron potentials
determined by Arthur and Young. /16/
***** JENDL-4 *********************************************
For mt=2, the Legendre coefficients were revised by
taking account of fine-resolution experimental data /23,24/
and Hauser-Feshbach + coupled-channel optical model
calculations. The experimental data were averaged in the
energy interval of 5 or 10 keV between 40 keV and 2.5 MeV.
Above 2.5, new model calculations were adopted.
***********************************************************
mf=6 Energy-angle distributions of secondary particles
mt=16,22,28,91
Obtained from JENDL Fusion File (sincros-II/17/ cal-
culations).
mf=12 Photon multiplicities and transition probability arrays
mt=16,22,28,91,103,107
Multiplicities were calculated with gnash.
mt=102
Calculated with casthy.
For 27.5 keV and 570 keV, based on experimental data
measured by Igashira et al./18/
mf=14 Photon angular distributions
mt=16,22,28,51-77,91,102,103,107
Assumed to be isotropic.
mf=15 Photon energy distributions
mt=16,22,28,91,103,107
Calculated with gnash.
mt=102
Calculated with casthy.
For 27.5 keV and 570 keV, based on experimental data
measured by Igashira et al./18/
mf=33 Covariances of cross sections (ref.19)
mt=1
Based on experimental data/3,4,5/. A chi-value was 1.96.
***** JENDL-4 **********************************************
Below 850 keV, the covariances were firstly estimated from
the experimental data /24-28/. Then, the estimated
variances were modified by considering the difference
between the average of the experimental data and that of the
total cross section in JENDL-4. Above 850, the covariances
in JENDL-3.3 were used, although the variances were
increased by comparing with the experimental data/3,4.5/.
No correlation was assumed between the region below 850 keV
and that above 850 keV.
************************************************************
mt=2
Constructed from mt=1, 16, 22, 28, 51-91, 102, 103, and 107.
mt=4
Constructed from mt=51-77,91.
mt=16
the covariances were obtained by using kalman. A chi-value
was 0.7.
mt=22
The covariances were obtained by using kalman. A chi-value
was 0.7.
mt=28
The covariances were obtained by using kalman. A chi-value
was 0.7.
mt=51-77,91
The covariances were obtained by using kalman. A chi-value
was 1.9.
************************************************************
In JENDL-4, variances for MT=51,53,54,55,56,58,61,62,63,64,
65,67,73,75,77,91 were revised by considering the spread of
experimental data.
************************************************************
mt=102
The covariances were obtained by using kalman. A chi-value
was 2.45.
mt=103
Based on experimental data. A chi-value was 4.99.
mt=107
The covariances were obtained by using kalman. A chi-value
was 0.7.
mf=34 Covariances of angular distributions (ref.19)
mt=2
The covariances of p1 coefficients were obtained by using
kalman. A chi-value was 1.95.
References
1) Chiba S. et al.: JAERI-M 92-027, p.35 (1992).
2) Nordborg C. and Salvatores M.: Proc. Int. Conf. Nuclear Data
for Science and Technology, Gatlinburg 1994, Vol.2, p.680
(1994).
3) Berthold K. et al.: Taken from EXFOR (1995).
4) Carlson A.D. and Cerbone R.J.: Nucl. Sci. Eng., 42, 28
(1970).
5) Perey F.G. et al.: ORNL-4823 (1972).
6) Young P.G. and Arthur E.D.: LA-6974 (1977).
7) Shibata K.: Private communication (2000).
8) Shibata K. and Fu. C.Y.: ORNL/TM-10093 (1986).
9) Igarasi S. : J. Nucl. Sci. Technol., 12, 67 (1975).
10) Voss F. et al.: Proc. Third Conf. on Neutron Cross Sections
and Technology, 1971, Knoxville, p.218 (1971).
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14) Smith D.L. and Meadows J.W.: Nucl. Sci. Eng., 58, 314 (1975).
15) Ikeda Y. et al.: JAERI 1312 (1988).
16) Arthur E.D. and Young P.G.: LA-8626-MS (1980).
17) Yamamuro N.: JAERI-M 90-006 (1990).
18) Igashira M. et al.: Proc. Int. Conf. Nuclear Data for
Science and Technology, Mito 1988, p.67 (1988).
19) Shibata K. et al.: JAERI-Research 97-074 (1997).
20) Ichihara A. et al.: JAEA-Data/Code 2007-012 (2007).
21) Soukhovitski E.Sh. et al.: JAERI-Data/Code 2005-002 (2005).
22) Kunieda S. et al.: J. Nucl. Sci. Technol., 44, 838 (2007).
23) Kinney W.E. and McConnell J.W.: Proc. Int. Conf. Interactions
of Neutrons with Nuclei, Lowell 1976, p.1319 (1976).
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and Technology, Juelich 1991, p.41 (1992).
25) Harvey J.A. et al.: DOE-NDC-33, 142 (1984).
26) Shcherbakov O.A. et al.: Yadernye Konstanty, 25, 51 (1977).
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28) Havens,Jr. W.W and Rainwater L.J.: Phys. Rev., 83,1123 (1951).