30-Zn- 65 JAEA EVAL-Dec09 N.Iwamoto
DIST-MAY10 20100327
----JENDL-4.0 MATERIAL 3028
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
History
09-12 The data above the resolved resonance region were evaluated
and compiled by N.Iwamoto.
MF= 1 General information
MT=451 Descriptive data and directory
MF= 2 Resonance parameters
MT=151 Resolved and unresolved resonance parameters
No resolved resonance parameters
Unresolved resonance region : 140 eV - 110 keV
The unresolved resonance paramters (URP) were determined by
ASREP code /1/ so as to reproduce the evaluated total and
capture cross sections calculated with optical model code
OPTMAN /2/ and CCONE /3/. The unresolved parameters
should be used only for self-shielding calculation.
Thermal cross sections and resonance integrals at 300 K
----------------------------------------------------------
0.0253 eV res. integ. (*)
(barn) (barn)
----------------------------------------------------------
Total 7.2310e+01
Elastic 6.1686e+00
n,gamma 6.4023e+01 3.9187e+01
n,p 3.0592e-03
n,alpha 2.0007e+00
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
MF= 3 Neutron cross sections
MT= 1 Total cross section
Sum of partial cross sections.
MT= 2 Elastic scattering cross section
Obtained by subtracting non-elastic scattering cross sections
from total cross section.
MT= 4 (n,n') cross section
Calculated with CCONE code /3/.
MT= 16 (n,2n) cross section
Calculated with CCONE code /3/.
MT= 22 (n,na) cross section
Calculated with CCONE code /3/.
MT= 24 (n,2na) cross section
Calculated with CCONE code /3/.
MT= 28 (n,np) cross section
Calculated with CCONE code /3/.
MT= 32 (n,nd) cross section
Calculated with CCONE code /3/.
MT= 41 (n,2np) cross section
Calculated with CCONE code /3/.
MT= 51-91 (n,n') cross section
Calculated with CCONE code /3/.
MT=102 Capture cross section
Calculated with CCONE code /3/.
MT=103 (n,p) cross section
Calculated with CCONE code /3/.
MT=104 (n,d) cross section
Calculated with CCONE code /3/.
MT=105 (n,t) cross section
Calculated with CCONE code /3/.
MT=106 (n,He3) cross section
Calculated with CCONE code /3/.
MT=107 (n,a) cross section
Calculated with CCONE code /3/.
The cross section at thermal energy was evaluated so as to
reproduce the value recommended by Mughabghab/4/.
MT=108 (n,2a) cross section
Calculated with CCONE code /3/.
MT=111 (n,2p) cross section
Calculated with CCONE code /3/.
MT=112 (n,pa) cross section
Calculated with CCONE code /3/.
MT=115 (n,pd) cross section
Calculated with CCONE code /3/.
MT=116 (n,pt) cross section
Calculated with CCONE code /3/.
MF= 4 Angular distributions of emitted neutrons
MT= 2 Elastic scattering
Calculated with CCONE code /3/.
MF= 6 Energy-angle distributions of emitted particles
MT= 16 (n,2n) reaction
Calculated with CCONE code /3/.
MT= 22 (n,na) reaction
Calculated with CCONE code /3/.
MT= 24 (n,2na) reaction
Calculated with CCONE code /3/.
MT= 28 (n,np) reaction
Calculated with CCONE code /3/.
MT= 32 (n,nd) reaction
Calculated with CCONE code /3/.
MT= 41 (n,2np) reaction
Calculated with CCONE code /3/.
MT= 51-91 (n,n') reaction
Calculated with CCONE code /3/.
MT=102 Capture reaction
Calculated with CCONE code /3/.
*****************************************************************
Nuclear Model Calculation with CCONE code /3/
*****************************************************************
Models and parameters used in the CCONE calculation
1) Optical model
* coupled channels calculation
coupled levels: 0,5 (see Table 1)
* optical model potential
neutron omp: Kunieda,S. et al./5/ (+)
proton omp: Koning,A.J. and Delaroche,J.P./6/
deuteron omp: Lohr,J.M. and Haeberli,W./7/
triton omp: Becchetti Jr.,F.D. and Greenlees,G.W./8/
He3 omp: Becchetti Jr.,F.D. and Greenlees,G.W./8/
alpha omp: Huizenga,J.R. and Igo,G./9/
(+) omp parameters were modified.
2) Two-component exciton model/10/
* Global parametrization of Koning-Duijvestijn/11/
was used.
* Gamma emission channel/12/ was added to simulate direct
and semi-direct capture reaction.
3) Hauser-Feshbach statistical model
* Width fluctuation correction/13/ was applied.
* Neutron, proton, deuteron, triton, He3, alpha and gamma
decay channel were taken into account.
* Transmission coefficients of neutrons were taken from
optical model calculation.
* The level scheme of the target is shown in Table 1.
* Level density formula of constant temperature and Fermi-gas
model were used with shell energy correction/14/.
Parameters are shown in Table 2.
* Gamma-ray strength function of standard Lorentzian form
was used for E1 transition.
For M1 and E2 transitions the standard Lorentzian form was
adopted. The prameters are shown in Table 3.
------------------------------------------------------------------
Tables
------------------------------------------------------------------
Table 1. Level Scheme of Zn-65
-------------------
No. Ex(MeV) J PI
-------------------
0 0.00000 5/2 - *
1 0.05393 1/2 -
2 0.11513 3/2 -
3 0.20694 3/2 -
4 0.76870 5/2 -
5 0.86421 7/2 - *
6 0.86692 1/2 -
7 0.90965 3/2 -
8 1.04739 5/2 -
9 1.06210 5/2 +
10 1.06551 9/2 +
11 1.25266 7/2 -
12 1.26342 9/2 -
13 1.34385 5/2 -
14 1.36908 5/2 +
15 1.46973 3/2 -
16 1.57705 3/2 -
17 1.58808 7/2 -
18 1.60300 5/2 -
-------------------
*) Coupled levels in CC calculation
Table 2. Level density parameters
--------------------------------------------------------
Nuclide a* Pair Eshell T E0 Ematch
1/MeV MeV MeV MeV MeV MeV
--------------------------------------------------------
Zn- 66 9.4000 2.9542 0.7967 1.1121 -0.5948 11.1189
Zn- 65 10.1000 1.4884 0.5412 1.0267 -1.5890 8.8932
Zn- 64 9.4000 3.0000 -0.5895 1.3122 -2.1371 14.8774
Cu- 65 8.5438 1.4884 0.5181 1.1578 -1.5153 9.2308
Cu- 64 9.0000 0.0000 -0.2574 1.1602 -3.0278 8.1946
Cu- 63 9.6000 1.5119 -0.7921 1.1891 -2.1218 11.0245
Cu- 62 8.5999 0.0000 -1.6978 1.3701 -3.8967 11.5298
Ni- 64 9.2000 3.0000 0.5302 1.0082 0.8446 9.1343
Ni- 63 9.7000 1.5119 0.1580 1.0041 -0.8012 7.9800
Ni- 62 8.7000 3.0480 -0.7667 1.2725 -0.5439 12.7980
Ni- 61 9.6000 1.5364 -1.2520 1.1257 -1.0688 9.6338
Ni- 60 8.5000 3.0984 -2.2445 1.4738 -1.5214 16.9599
--------------------------------------------------------
Table 3. Gamma-ray strength function for Zn- 66
--------------------------------------------------------
* E1: ER = 16.23 (MeV) EG = 3.27 (MeV) SIG = 41.40 (mb)
ER = 19.19 (MeV) EG = 5.98 (MeV) SIG = 56.10 (mb)
* M1: ER = 10.15 (MeV) EG = 4.00 (MeV) SIG = 2.86 (mb)
* E2: ER = 15.59 (MeV) EG = 5.32 (MeV) SIG = 1.53 (mb)
--------------------------------------------------------
References
1) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)
[in Japanese].
2) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004).
3) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).
4) Mughabghab,S.F.: "Atlas of Neutron Resonances, Fifth Edition:
Resonance Parameters and Thermal Cross Sections. Z=1-100",
Elsevier Science (2006).
5) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).
6) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)
[Global potential].
7) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).
8) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.
J.H.Williams Lab., Univ. Minnesota (1969).
9) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962).
10) Kalbach,C.: Phys. Rev. C33, 818 (1986).
11) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).
12) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).
13) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).
14) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151
(1994).