28-Ni- 58 NAIG EVAL-MAR87 S.IIJIMA
DIST-MAY10 20091112
----JENDL-4.0 MATERIAL 2825
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 Evaluation was performed for JENDL-3. Short description
on the evaluation is given in ref./1/
87-05 Compiled by K.Shibata (jaeri).
90-10 mf=5, mt=16, 22 and 28: data at threshold energies were
modified. mf=12, mt=16, 91 and 102 were slightly modified.
93-09 JENDL-3.2.
Compiled by T.Nakagawa (ndc/jaeri)
***** modified parts for JENDL-3.2 ********************
(4,16-28), (4,91) Taken from JENDL fusion file
(5,16-91) Taken from JENDL fusion file
(12,102) Below 500 keV, revised by S.Igasasi
(15,102) Below 500 keV, revised by S.Igarasi
***********************************************************
-------------------------------------------------------------
JENDL fusion file /2/ (as of Sep. 1993)
Evaluated by S.Chiba (ndc/jaeri)
Compiled by S.Chiba
All of cross sections were taken from JENDL-3. EDX's of
mt=16, 22, 28 and 91 were replaced by those calculated
with sincros-II code system/3/ in order to make the
agreement with the EDX of natural Ni measured by Baba et
al./4/ at 14.1 MeV. DDX's of continuum reactions were
created with f15tob program /2/. Kumabe's systematics
/5/ was used. The precompound/compound ratio was
calculated by the sincros-II code system.
Optical-model, level density and other parameters used
in the sincros-ii calculation are described in ref./3/.
Level schemes were determined on the basis of ENSDF/6/.
-------------------------------------------------------------
2000-05 Re-evaluated by N.Yamamuro (TIT), and compiled by
K.Shibata (jaeri).
*************** modification for JENDL-3.3 **************
(3,1) Re-evaluated above 557 keV
(3,2) Re-calculcated.
(3,16),(3,22),(3,28), Calculated by sincros-II
(3,103),(3,104),(3,105), Calculated by sincros-II
(3,106),(3,107),(3,111), Calculated by sincros-II
(3,203),(3,204),(3,205) Calculated by sincros-II
(3,206),(3,207) Calculated by sincros-II
(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 fusion file
(6,203),(6,204),(6,205), Taken from JENDL fusion file
(6,206),(6,207) Taken from JENDL fusion file
(12,102) Modified
(15,102) Modified
*********************************************************
2001-03 Resonance parameters were taken from the work of Perey
et al./7/
2002-01 Covarinaces were taken from the work of Shibata and
Oh./15/
2009-11 Total cross sections were re-calculated from partial
cross sections for JENDL-4.0.
mf=1,mt=451 Comments and dictionary
mf=2,mt=151 Resolved resonance parameters : 1.0e-5 eV - 812 keV
Based on the work of Perey et al./7/
The Reich-Moore formula was employed.
calculated 2200 m/s values and resonance integrals (barn):
2200 m/s value res. int.
total 29.422 -
elastic 24.802 -
capture 4.619 2.21
mf=3 Neutron cross sections
Small ackground cross sections, which were taken from ENDF/B-VI,
were applied to the resonance region for mt=1, 2, 102.
Cross sections above 812 keV were evaluated as follows:
mt=1 : Total cross section
Above 812 keV, evaluation was based on the natural Ni data
measured by Larson et al. /8/ with unfolding considering
experimental resolution.
mt=2 : Elastic scattering
(total) - (nonelastic cross sections).
mt=3 : Nonelastic cross section
Sum of mt=4,16,22,28,102,103,104,105,106,107,111.
mt=16 (n,2n)
Evaluated by N. Yamamuro /9/ by using sincros-II code.
mt=22 (n,n'a)
Evaluated by N. Yamamuro /9/ by using sincros-II code.
mt=28 (n,n'p)
Evaluated by N. Yamamuro /9/ by using sincros-II code.
mt=4,51-65,91 Inelastic scattering
The casthy /10/ and gnash /11/ calculation was adopted in
the neutron energy region below and above 7 MeV, respec-
tively. the direct process was taken into account for mt=
51, 52, 53, 55 and 65. For the level of mt=65, only the
direct process was considered. The level scheme used is
given as follows:
no energy(MeV) spin-parity
g.s 0.0 0 +
1. 1.4545 2 +
2. 2.4591 4 +
3. 2.7755 2 +
4. 2.9018 1 +
5. 2.9424 0 +
6. 3.0376 2 +
7. 3.2634 2 +
8. 3.4203 3 +
9. 3.5240 4 +
10. 3.5309 0 +
11. 3.5934 1 +
12. 3.6200 4 +
13. 3.7744 3 +
14. 3.8983 2 +
15. 4.4753 3 -
continuum levels assumed above 3.932 MeV.
Potential parameters are given as follows /12/:
V =51.33 - 0.331*En ,Ws=8.068 + 0.112*En ,Vso=7.0 (MeV)
r0=rso=1.24 ,rs=1.40 (fm)
a0=aso=0.541 ,as=0.4 (fm)
Surface imaginary part is in derivative Woods-Saxon form.
mt=102 Capture
Calculated with casthy. The gamma-ray strength function
of 4.616e-5 was used. Level density parameters are:
pairing spin-cutoff f.
a(1/MeV) T(MeV) energy(MeV) (MeV**0.5) Ex(MeV)
-------------------------------------------------------------
ni-58 6.850 1.30 2.47 5.726 9.610
ni-59 7.126 1.325 1.20 5.907 9.250
-------------------------------------------------------------
mt=103 (n,p)
Evaluated by N. Yamamuro /9/ by using sincros-II code.
mt=104,105,106,107 (n,d),(n,t),(n,he-3),(n,a)
Evaluated by N. Yamamuro /9/ by using sincros-II code.
mt=111 (n,2p)
The cross section was calculated using pegasus code /13/.
Taken from JENDL-3.2.
mt=203,204,205,206,207
Calculated from the cross sections mentioned above.
mf=4 Angular distributions of secondary neutrons
mt=2 : Calculated with optical model.
mt=51-64 : Calculated with casthy. direct process
included in mt=51, 52, 53, 55.
mt=65 : c.c. calculation.
mf=5 Energy-angle distributions of secondary particles
mt=16,22,28,91,203,204,205,206,207
Taken from JENDL fusion file.
mf=12 Photon multiplicities and transition probability arrays
mt=16,22,28,91,103,107:
Multiplicities calculated with gnash.
mt=51-65 : Transition probability arrays.
mt=102 : Multiplicities calculated from energy balance.
mf=14 Photon angular distributions
mt=16,22,28,51-65,91,102,103,107:
Isotropic distributions.
mf=15 Photon energy distributions
mt=16,22,28,91,102,103,107:
Calculated with gnash. For mt=102, spectra were
calculated with casthy, taking primary transitions
at 1.0e-5, 2.53e-2, 1.0e+3 and 1.0e+4 eV.
Between 16 keV and 550 keV for mt=102, the
measurements for natural Ni /14/ are given.
In JENDL-3.3, for mt=102, the spectra above 1 MeV
were replaced by new calculations /9/
mf=33 Covariances of cross sections (ref.15)
mt=1
Based on experimental data. A chi-value was 2.99.
mt=2
Constructed from mt=1, 16, 22, 28, 51-91, 102, 103, 104, 105,
and 107.
mt=4
Constructed from mt=51-65, 91.
mt=16
Based on experimental data. A chi-value was 0.8.
mt=22, 28, 104, 105, 107
The covariances were obtained by using kalman. A chi-value
was 2.67.
mt=51-65, 91
The covariances were obtained by usign kalman. A chi-value
was 10.9.
mt=102
The covariances were obtained by usign kalman. A chi-value
was 0.2.
mt=103
Based on experimental data. A chi-value was 8.5.
mf=34 Covariances of angular distributions (ref.15)
mt=2
The covariances of p1 coefficients were obtained by using
kalman. A chi-value was 0.84.
References
1) Iijima S. et al.: Proc. Int. Conf. Nuclear Data for Science
and Technol., Mito, 1988, p.627 (1988).
2) Chiba S. et al.: JAERI-M 92-027, p.35 (1992).
3) Yamamuro N.: JAERI-M 90-006 (1990).
4) Baba M. et al.: Proc. Int. Conf. Nuclear Data for Science
and Technol., Mito, 1988, p.291 (1988).
5) Kumabe I. et al.: Nucl. Sci. Eng., 104, 280 (1990).
6) ENSDF: Evaluated Nuclear Structure Data File, BNL/NNDC.
7) Perey C.M. et al.: ORNL/TM-10841 (1988).
8) Larson D.C. et al.: ORNL-TM-8203 (1983).
9) Yamamuro N.: Private communication (2000).
10) Igarasi S. and Fukahori T.: JAERI 1321 (1991).
11) Young P.G. and Arthur E.D.: LA-6947 (1977).
12) Kawai M. : unpublished.
13) Iijima S. et al.: JAERI-M 87-025, p.337 (1987).
14) Igashira M.: Private communication (2000).
15) Shibata K. and Oh S.Y.: JAERI-Research 2000-007 (2000).