28-NI- 61 NAIG EVAL-MAR87 S.IIJIMA
DIST-MAR02 REV4-MAY00 20020208
----JENDL-3.3 MATERIAL 2834
-----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: Data at threshold energies were 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
***********************************************************
-------------------------------------------------------------
JENDL fusion file /2/ (as of Sep. 1993)
Evaluated by S.Chiba (ndc/jaeri)
Compiled by S.Chiba
Cross sections were taken from JENDL-3.1. EDX's of
mt=16, 22, 28 and 91 were replaced by those calculated
with sincros-II code system/3/ because normalization
errors were found in the data stored in JENDL-3.1. DDX's
of continuum reactions were created with f15tob program
/2/ where Kumabe's systematics /4/ 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/5/.
-------------------------------------------------------------
2000-05 Re-evaluated by N.Yamamuro (TIT), and compiled by
K.Shibata (jaeri).
*************** modification for JENDL-3.3 **************
(3,1) Re-evaluated above 1.5 MeV
(3,2) Re-calculcated.
(3,16),(3,17),(3,22),(3,28), Calculated by sincros-II
(3,32) Calculated by sincros-II
(3,51-91) Calculated by sincros-II
(3,103),(3,104),(3,105), Calculated by sincros-II
(3,106),(3,107), Calculated by sincros-II
(3,203),(3,204),(3,205) Calculated by sincros-II
(3,206),(3,207) Calculated by sincros-II
(3,251) Deleted
(4,17),(4,32) Isotropic distribution
(4,51-68) Isotropic distribution
(5,16),(5,17),(5,22),(5,28), Calculated by sincros-II
(5,32),(5,91) Calculated by sincros-II
(12,16-107) Calculated by sincros-II
(14,16-107) Isotropic distribution
(15,16-107) Calculated by sincros-II
*********************************************************
mf=1,mt=451 Comments and dictionary
mf=2,mt=151 Resolved resonance parameters : 1.0e-5 eV - 57.0keV
Parameters were taken from JENDL-2 except that the neutron
width of the 64.07-keV s-wave resonance was changed from
54.0 eV to 535 eV /6/.
Scattering radius: 6.4 fm
calculated 2200 m/s values and resonance integrals (barn):
2200 m/s value res.int
total 11.239 -
elastic 8.731 -
capture 2.509 2.44
mf=3 Neutron cross sections
Background cross sections were applied to the resonance region.
Cross sections above 57.0 keV were evaluated as follows :
mt=1 : Total cross section
High-resolution experimental data/7/ were adopted between
57 keV and 74.6 keV. Above 74.6 keV up to 1.5 MeV, the
JENDL-3.2 data were adopted.
Above 1.5 MeV, 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=16,17,22,28,32,103,104,105,106,107 (n,2n),(n,3n),(n,n'a),
(n,np),(n,nd),(n,p),(n,d),(n,t),(n,he-3),(n,a)
Calculated by N. Yamamuro /9/ with sincros-II/3/.
mt=4,51-68,91 : Inelastic scattering
Calculated with sincros-II.
The level scheme used is as follows:
no energy(MeV) spin-parity
g.s 0.0 3/2 -
1. 0.0674 5/2 -
2. 0.2830 1/2 -
3. 0.6560 3/2 -
4. 0.9086 5/2 -
5. 1.0152 7/2 -
6. 1.0996 3/2 -
7. 1.1323 5/2 -
8. 1.1852 3/2 -
9. 1.4560 7/2 -
10. 1.6096 5/2 -
11. 1.7295 3/2 -
12. 1.8077 7/2 -
13. 1.9880 9/2 +
14. 1.9976 3/2 -
15. 2.0180 7/2 -
16. 2.1216 9/2 +
17. 2.1235 1/2 -
18. 2.1292 11/2 -
Continuum levels assumed above 2.4097 MeV.
mt=102: Capture
Calculted with casthy code /10/. Taken from JENDL-3.2.
mt=111: (n,2p)
Taken from JENDL-3.2.
mt=203,204,205,206,207
Calculated from the cross sections given above.
mf=4 Angular distributions of secondary neutrons
mt=2 : Calculated with optical model.
Taken from JENDL-3.2.
mt=16,22,28,91: Approximately transformed from the mf=6 data
(DDX) of JENDL fusion file.
mt=17,32 : Isotropic distribution.
mt=51-68 : Isotropic distribution.
mf=5 Energy distributions of secondary neutrons
mt=16,17,22,28,32,91: Calculated by N.Yamamuro /9/.
mf=12 Photon multiplicities and transition probability arrays
mt=16,17,22,28,91,103,104,107:
Multiplicities calculated with sincros-II.
mt=102 : Multiplicities calculated from energy balance.
mt=51-68 : Transition probability arrays
mf=14 Photon angular distributions
mt=16,17,22,28,51-68,91,102,103,104,107
Isotropic distributions.
mf=15 Photon energy distributions
mt=16,17,22,28,91,102,103,104,107:
Calculated with sincros-II.
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) Kumabe I. et al.: Nucl. Sci. Eng., 104, 280 (1990).
5) ENDSF: Evaluated Nuclear Structure Data File, BNL/NNDC.
6) Moxon M.C.: KfK-2046, p.156 (1975).
7) Cho M. et al.: Proc. 2nd Int. Conf. Nucl. Data for Reactors,
Helsinki, 1970, Vol.1, p.619 (1970).
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).