26-Fe- 58
26-Fe- 58 JNDC EVAL-MAR87 S.IIJIMA,H.YAMAKOSHI
DIST-MAY10 20090904
----JENDL-4.0 MATERIAL 2637
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
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The data were taken from JENDL-3.3.
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HISTORY
87-03 Evaluation was performed for JENDL-3.
87-05 Compiled by K.Shibata (jaeri).
93-10 JENDL-3.2.
Re-evaluation was made by
T.Nakagawa (ndc/jaeri): resonance params, cross sections
S.igarasi (nedac): gamma-ray production data below 10 keV
Compiled by T.Nakagawa
***** Modified parts for JENDL-3.2 ********************
(2,151)
(3,1), (3,2), (3,4), (3,51-91), (3,102)
(4,16-28), (4,91) taken from JENDL Fusion File
(12,102)
(15,102) below 1 MeV
***********************************************************
-------------------------------------------------------------
JENDL Fusion File /1/ (as of aug. 1993)
Evaluated B.Yu (ciae) and S.Chiba (ndc/jaeri)
compiled by B.Yu.
All of cross sections were taken from JENDL-3. Mf=6
of mt=16, 22, 28 and 91 were created with sincros-II /2/
and f15tob/1/ program. Kalbach's systematics /3/ was
used. The precompound/compound ratio was taken from the
sincros-II calculation.
Optical-model, level density and other parameters used
in the sincros-II calculation are described in ref./2/.
Level schemes were determined on the basis of ENSDF/4/.
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2000-03 Modification for JENDL-3.3
Reevaluated and compiled by K. Shibata (jaeri).
************** modified parts *******************************
(2,151) changed to Reich-Moore formula
(3,203),(3,207) calculated
(6,16),(6,22),(6,28),(6,91) taken from JENDL/F-99/1/
(6,203),(6,207) taken from JENDL/F-99/1/
*************************************************************
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 350.0 keV
The Reich Moore formula was used. Parameters were
determined on the basis of data by Garg et al./5/,
Kaeppeler et al./6/, Allen and Macklin/7/.
calculated 2200-m/s cross sections and res. integrals.
2200-m/s res. integ.
elastic 6.470 b -
capture 1.300 b 1.36 b
total 7.770 b -
mf=3 Neutron cross sections
Bbelow 350 keV, no background cross sections were given.
Above 350 keV, the data were evaluated as follows.
mt=1,4,51-62,91,102 Total, inelastic and capture
Calculated with optical and statistical model code casthy
/8/. Optical potential parameters/9/ are as follows:
V = 46.0-0.25*En (MeV),
Ws = 14.0-0.2*En (MeV), (in the Gaussian form)
Wi = 0.125*E-0.0004*E**2 (MeV),
Vso= 6.0 (MeV),
r = 1.286 (fm), a0 = 0.62 (fm)
rs = 1.387 (fm), as = 0.7 (fm)
rso= 1.07 (fm), aso= 0.62 (fm)
The level scheme used is:
no. energy(mev) spin-parity
g.s. 0.0 0 +
1. 0.8108 2 +
2. 1.6747 2 +
3. 2.0765 4 +
4. 2.1339 3 +
5. 2.2581 0 +
6. 2.6004 4 +
7. 2.7819 1 +
8. 2.8764 2 +
9. 3.0840 2 +
10. 3.1330 4 +
11. 3.2330 2 +
12. 3.2440 0 +
Levels above 3.389 MeV were assumed to be overlapping.
the capture cross section was normalized to 3 mb at 500
keV/10/. Direct capture cross section was calculated
with a simple formula derived by Benzi and Reffo/11/ and
added to the casthy calculation.
mt=2 Elastic
Total cross section - sum of partial cross sections
mt=16,22,28,103,107 (n,2n),(n,n'a),(n,n'p),(n,p),(n,a)
Calculated with gnash /12/.
mt=203
Sum of mt=28 and 103.
mt=207
Sum of mt=22 and 107.
mf=4 Angular distributions of secondary neutrons
mt=2,51-62
Casthy calculation
mf=6 Energy-angle distributions of secondary particles
mt=16,22,28,91,203,207
Calculated with gnash.
mf=12 Photon multiplicities and trasition probabilities
mt=16,22,28,91,103,107
Multiplicities were calculated with gnash.
mt=51-62
Transition probabilities were given.
mt=102
Multiplicities were calculated from energy balance.
mf=14 Photon angular distributions
mt=16,22,28,51-62,91,102,103,107
Assumed to be isotropic.
mf=15 Photon energy distributions
mt=16,22,28,91,103,107
Calculated with gnash.
mt=102
Below 10 keV, calculated with casthy/8/. Above 1 MeV, gnash
calculation was adopted.
References
1) Chiba S. et al.: JAERI-M 92-027, p.35 (1992).
2) Yamamuro N.: JAERI-M 90-006 (1990).
3) Kalbach C.: Phys. Rev., C37, 2350 (1988).
4) ENSDF: Evaluated nuclear structure data file, BNL/NNDC.
5) Garg J.B. et al.: Phys. Rev., C18, 1141 (1978).
6) Kaeppeler F. et al.: Nucl. Sci. Eng., 84, 234 (1983).
7) Allen B.J. and Macklin R.L.: J. Phys. G., 6, 381 (1980).
8) Igarasi S. and Fukahori T.: JAERI 1321 (1991).
9) Yamakoshi H.: JAERI 1261, p.30 (1979).
10) Trofimov Ju.N.: Atomnaja Energija, 58, 278 (1985).
11) Benzi V. and Reffo G.: CCDN/NW/10 (1969).
12) Young P.G. and Arthur E.D.: LA-6974 (1977).