26-Fe- 54
26-Fe- 54 JNDC EVAL-MAR87 S.IIJIMA,H.YAMAKOSHI
DIST-MAY10 20090904
----JENDL-4.0 MATERIAL 2625
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 Evaluation was performed for JENDL-3.
87-05 Compiled by K.Shibata (jaeri).
93-11 JENDL-3.2
The cross sections for mt=54,55 were modified by
K. Shibata (jaeri).
The Q-value of mt=102 was corrected.
Angular distributions for mt=16,22,28,91 were obtained
from the JENDL Fusion File /1/ (kalbach's systematics).
The gamma production data were reevaluated by S. Igarasi
(nedac).
Data were compiled by K. Shibata.
***** modified parts for JENDL-3.2 *******************
(3,54),(3,55) Direct components
(3,102) Q-value corrected
(3,4) Recalculated
(3,2) Total - nonelastic
(4,16),(4,22),(4,28),(4,91)
Converted from JENDL fusion file
(12,28),(12,102),(12,103)
Multiplicities corrected
(15,102) Newly calculated below 10 keV
*******************************************************
2000-04 Re-evaluated and compiled by K.Shibata (jaeri).
********* modified parts for JENDL-3.3 *****************
(1,451) Modified
(2,151) Taken from ENDF/B-VI.6
(3,1) Re-evaluaed
(3,2) Re-calculated
(3,102) Pre-equilibrium capture included
(3,103) Taken from JENDL/D-99 /2/
(3,251) Deleted
(4,2) 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/
********************************************************
2009-09 Compiled by K.Shibata (jaea).
********************************************************
(1,451) Modified
(3,1) Recalculated
(3,4) Recalculated from partial (n,n')
This was done to pass the sumup
check in FIZCON.
********************************************************
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 700.0 keV
The Reich-Moore formula was used. Parameters were taken
from ENDF/B-VI.6.
calculated 2200-m/s cross sections and res. integrals.
2200-m/s res. integ.
elastic 2.181 b -
capture 2.251 b 1.212 b
total 4.432 b -
mf=3 Neutron cross sections
Below 700 keV, background cross sections were given for the
total and capture cross sections.
Above 700 keV, the cross sections were evaluated as
follows.
mt=1 Total
Between 700 keV and 7 MeV, the cross sections were obtained
from the data on Fe-54 measured by Cornelis et al. /3/
Above 7 MeV, the cross sections were evaluated by
a least-squares fitting to the measurements by Cornelis
et al./3/ and Carlton et al. /4/
mt=2 Elastic scattering
Given as total minus other cross sections
mt=16,22,28 (n,2n),(n,n'a),(n,n'p)
Calculated using the gnash code /5/.
mt=4,51-69,91 Inelastic scattering
Below 7 MeV, the cross sections were calculated using
casthy /6/ with width fluctuation corrections.
Above 7 MeV, the gnash calculation was performed.
For mt=51,52,53,55,59,68, the direct process
component was considered by the c.c. theory.
Level scheme is given as follows:
no. energy(MeV) spin-parity
g.s. 0.0 0 +
1. 1.4082 2 +
2. 2.5382 4 +
3. 2.5613 0 +
4. 2.9499 6 +
5. 2.9590 2 +
6. 3.1661 2 +
7. 3.2952 4 +
8. 3.3450 3 -
9. 3.8338 4 +
10. 4.0330 4 +
11. 4.0472 4 +
12. 4.0720 3 +
13. 4.2632 4 +
14. 4.2961 0 +
15. 4.5980 2 +
16. 4.6550 2 +
17. 4.7000 3 +
18. 4.7800 3 -
19. 4.9490 4 +
Continuum levels were assumed above 5.145 MeV.
Optical potential parameters are as follows:
V = 46.0-0.250*E , r0=1.286, a0=0.620
Ws = 14.00-0.200*E , rs=1.390, as=0.700
Vso= 6.00 , rso=1.070,aso=0.620
(energies in MeV, lengths in fm)
mt=102 Capture
Casthy calculation was adopted.
Above 5 MeV, the pre-equilbrium capture process was
considered /7/.
mt=103 (n,p)
The cross sections were obtained from a lease-squares fit
to the experimental data/8/-/34/ by using the GMA
code /35/.
mt=107 (n,alpha)
Gnash calculation multiplied by 0.94.
mf=4 Angular distributions of secondary neutrons
mt=2,51-69
Optical and statistical-model calculation.
For mt=51,52,53,54,59,68, the direct-process component
was taken into account by the c.c. theory.
mf=6 Energy-angle distributions of secondary particles
mt=16,22,28,91
Calculated with gnash.
mf=12 Photon multiplicities and transition probability arrays
mt=16,22,28,91,102,103,107
Multiplicities were calculated with gnash.
For mt=28,102,103, corrections were made.
mt=51-69
Transition probability arrays
mf=14 Photon angular distributions
mt=16,22,28,51-69,91,102,103,107
Assumed to be isotropic.
mf=15 Photon energy distributions
mt=16,22,28,91,102,103,107
Calculated with gnash.
For mt=102, replaced with new calculations below 10 keV.
References
1) Chiba S. et al.: JAERI-M 92-027, p.35 (1992).
2) JAERI Nuclear Data Center: "JENDL Dosimetry File 99",
private communication (1999).
3) Cornelis E. et al.: Proc. Int. Conf. Nuclear Data for
Science and Technology, Antwerp 1982, p.135 (1983).
4) Carlton R.F. et al.: Bull. Am. Phys. Soc., 30, 1252 (1985).
5) Young P.G. and Arthur E.D.: LA-6974 (1977).
6) Igarasi S. : J. Nucl. Sci. Technol., 12, 67 (1975).
7) Shibata K.: Private communication (2000).
8) Smith D.L. and Meadows J.W.: Nucl. Sci. Eng., 58, 314 (1975).
9) Cross W.G. et al.: EANDC(CAN)-16,1 (1963).
10) Carroll E.E., Jr. and Smith G.G.: Nucl. Sci. Eng., 22, 411
(1965).
11) Salisbury S.R. and Chalmers R.A. : Phys. Rev., B140, 305
(1965).
12) Venugopala Rao P. and Fink R.W.: Phys. Rev.,154, 1023 (1967).
13) Saraf S.K. et al.: Nucl. Sci. Eng., 107, 365 (1991).
14) Greenwood L.R.: ASTM-STP-956, 743 (1987).
15) Lauber A. and Malmskog S.G. : Nucl. Phys., 73, 234 (1965).
16) Paulsen A. and Widera R.: Proc. Conf. Chemical Nuclear Data,
Measurements and Application, Canterbury, 1971.
17) Paulsen A. et al.: Nucl. Sci. Eng., 72, 113 (1979).
18) Bahal B.M. and Pepelnik R.: NEANDC(E)-252/U, p.28, (1984).
19) Bahal B.M. et al.: Proc. Int. Conf. Nuclear Data for Basic
and Applied Science, Santa Fe 1985, p.211 (1986).
20) Ikeda Y. et al.: JAERI-1312 (1988).
21) Ikeda Y. et al.: NEANDC(J)-155, p.11 (1990).
22) Kobayashi K. and Kimura I.: Proc. Int. Conf. Nuclear Data
for Science and Technology, Mito 1988, p.261 (1988).
23) Ai C.E. et al. : Nucl. Sci., Taiwan, 14, 1 (1977).
24) Garlea I. et al.: Revue Roumaine de Physique, 26, 643
(1981).
25) Viennot M. et al.: Proc. Int. Conf. Nuclear Data for
Science and Technology, Antwerp 1982, p.406 (1983).
26) Lu Han-lin et al.: Chinese Nucl. Phys. 4, 272 (1982).
27) Lu Han-lin et al.: INDC(CPR)-16 (1989); Chinese Nucl.
Phys. 7, 242 (1985).
28) Garlea I. et al.: ZFK-562, p.126 (1985); Revue Roumaine de
Physique, 31, 149 (1986).
29) Viennot M. et al.: Nucl. Sci. Eng., 108, 289 (1991).
30) Garlea I. et al.: Revue Roumaine de Physique, 37, 19
(1992).
31) Klochkova L.I. et al: Proc. 1st Int. Conf. Neutron Physics,
Kiev 1987, Vol.3, p.315 (1987).
32) Klochkova L.I. et al.: Proc. All Union Conf. Neutron
Physics, Kiev 1983, Vol.4, p.381 (1983).
33) Meadows J.W. et al.: Ann. Nucl. Energy, 23, 877 (1996).
34) Mannhart W.: INDC(GER)-40 (1996); private communication
(1998).
35) Poenitz W.P.: Proc. Conf. Nuclear Data Evaluation Methods
and Procedures, BNL 1980, BNL-NCS-51363, p.249 (1981).