28-Ni- 64
28-Ni- 64 NAIG EVAL-MAR87 S.IIJIMA
DIST-MAY10 20091112
----JENDL-4.0 MATERIAL 2843
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
===========================================================
The data were taken from JENDL-3.3.
===========================================================
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).
93-09 JENDL-3.2.
Compiled by T.Nakagawa (ndc/jaeri)
***** modified parts for JENDL-3.2 ********************
(3,106), (3,111) Deleted.
(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/ in which 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 557 keV
(3,2) Re-calculcated.
(3,16),(3,17),(3,22),(3,28), 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) Isotropic distribution
(4,51-68) Isotropic distribution
(5,16),(5,17),(5,22),(5,28), Calculated by sincros-II
(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 - 553 keV
Parameters were taken from JENDL-2.
Scattering radius: 6.4 fm
calculated 2200 m/s values and resonance integrals (barn):
2200 m/s value res.int
total 1.515 -
elastic 0.035 -
capture 1.480 0.820
mf=3 Neutron cross sections
Background cross sections were applied to resonance region.
Cross sections above 553 keV were evaluated as follows :
mt=1 : Total cross section
Experimental data of Farrell et al./6/ were adopted
between 553 keV and 557 keV.
Above 557 keV, evaluation was based on the natural Ni
data measured by Larson et al. /7/ with unfolding
considering experimental resolution.
mt=2 : Elastic scattering
(total) - (nonelastic cross section).
mt=16,17,22,28,103,104,105,106,107: (n,2n),(n,3n),(n,n'a),
(n,n'p),(n,p),(n,d),(n,t),(n,he-3),(n,a)
Calculated by N. Yamamuro /8/ with sincros-II/3/.
mt=4,51-70,91,102 : Inelastic scattering
Calculated by N. Yamamuro /8/ with sincros-II/3/.
The level scheme/9/ used is given as follows: 2
no energy(MeV) spin-parity
g.s 0.0 0 +
1. 1.3460 2 +
2. 2.2770 0 +
3. 2.6080 4 +
4. 2.8650 0 +
5 2.9710 2 +
6 3.0280 0 +
7 3.1650 4 +
8 3.2730 2 +
9. 3.3930 3 +
Continuum levels assumed above 3.459 MeV.
mt=102 : Capture
Calculated with the statistical model code casthy/10/.
The gamma-ray strength function of 7.67e-6 was obtained
from the capture cross section data of Beer and Spencer
/11/.
Level density parameters are:
pairing spin-cutoff f.
a(1/MeV) T(MeV) energy(MeV) (MeV**0.5) Ex(MeV)
-------------------------------------------------------------
Ni-64 9.300 1.02 2.70 7.124 8.940
Ni-65 10.95 0.86 1.20 7.870 6.400
-------------------------------------------------------------
mf=4 Angular distributions of secondary neutrons
mt=2 : Calculated with optical model.
Taken from JENDL-3.2.
mt=16,17,22,28,91: Approximately transformed from the mf=6 data
(DDX) of JENDL fusion file.
mt=51-59 : Isotropic in the center-of-mass system.
mf=5 Energy distributions of secondary neutrons
mt=16,17,22,28,91: Calculated with sincros-II.
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=51-59 : Transition probability arrays
mf=14 Photon angular distributions
mt=16,17,22,28,51-59,91,102,103,104,107
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) ENSDF: Evaluated Nuclear Structure Data File, BNL/NNDC.
6) Farrell J.A. et al.: Ann. Phys., 37, 367 (1966)
(EXFOR 11601009).
7) Larson D.C. et al.: ORNL-TM-8203 (1983).
8) Yamamuro N.: Private communication (2000).
9) Lederer C.M. and Shirley V.S.: Table of Isotopes, 7th ed.,
Wiley-Interscience (1978).
10) Igarasi S. and Fukahori T.: JAERI 1321 (1991).
11) Beer H. and Spencer R.R.: Nucl. Phys., A240, 29 (1975).