76-Os-189 JAEA EVAL-Jan10 N.Iwamoto
DIST-MAY10 20100121
----JENDL-4.0 MATERIAL 7640
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
History
10-01 The resolved resonance parameters were evaluated by
N.Iwamoto.
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
Resolved resonance region: below 76.3 eV
Resolved resonance parameters were taken from Mughabghab
/1/. The negative resonance was placed so as to
reproduce the cross sections at thermal energy recommended
by Mughabghab /1/.
Unresolved resonance region : 76.3 eV - 100 keV
The unresolved resonance paramters (URP) were determined by
ASREP code /2/ so as to reproduce the evaluated total and
capture cross sections calculated with optical model code
CCOM /3/ and CCONE /4/. 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 4.0554e+01
Elastic 1.5550e+01
n,gamma 2.5005e+01 8.0744e+02
n,alpha 2.2672e-05
----------------------------------------------------------
(*) 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 /4/.
MT= 16 (n,2n) cross section
Calculated with CCONE code /4/.
MT= 17 (n,3n) cross section
Calculated with CCONE code /4/.
MT= 22 (n,na) cross section
Calculated with CCONE code /4/.
MT= 24 (n,2na) cross section
Calculated with CCONE code /4/.
MT= 28 (n,np) cross section
Calculated with CCONE code /4/.
MT= 32 (n,nd) cross section
Calculated with CCONE code /4/.
MT= 33 (n,nt) cross section
Calculated with CCONE code /4/.
MT= 41 (n,2np) cross section
Calculated with CCONE code /4/.
MT= 51-91 (n,n') cross section
Calculated with CCONE code /4/.
MT=102 Capture cross section
Calculated with CCONE code /4/.
MT=103 (n,p) cross section
Calculated with CCONE code /4/.
MT=104 (n,d) cross section
Calculated with CCONE code /4/.
MT=105 (n,t) cross section
Calculated with CCONE code /4/.
MT=106 (n,He3) cross section
Calculated with CCONE code /4/.
MT=107 (n,a) cross section
Calculated with CCONE code /4/.
MF= 4 Angular distributions of emitted neutrons
MT= 2 Elastic scattering
Calculated with CCONE code /4/.
MF= 6 Energy-angle distributions of emitted particles
MT= 16 (n,2n) reaction
Calculated with CCONE code /4/.
MT= 17 (n,3n) reaction
Calculated with CCONE code /4/.
MT= 22 (n,na) reaction
Calculated with CCONE code /4/.
MT= 24 (n,2na) reaction
Calculated with CCONE code /4/.
MT= 28 (n,np) reaction
Calculated with CCONE code /4/.
MT= 32 (n,nd) reaction
Calculated with CCONE code /4/.
MT= 33 (n,nt) reaction
Calculated with CCONE code /4/.
MT= 41 (n,2np) reaction
Calculated with CCONE code /4/.
MT= 51-91 (n,n') reaction
Calculated with CCONE code /4/.
MT=102 Capture reaction
Calculated with CCONE code /4/.
*****************************************************************
Nuclear Model Calculation with CCONE code /4/
*****************************************************************
Models and parameters used in the CCONE calculation
1) Optical model
* coupled channels calculation
coupled levels: 0,3,6,11,22 (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 enhanced generalized
Lorentzian form/15/,/16/ 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 Os-189
-------------------
No. Ex(MeV) J PI
-------------------
0 0.00000 3/2 - *
1 0.03081 9/2 -
2 0.03618 1/2 -
3 0.06953 5/2 - *
4 0.09525 3/2 -
5 0.09735 11/2 +
6 0.21666 7/2 - *
7 0.21939 7/2 -
8 0.23356 5/2 -
9 0.27592 5/2 -
10 0.28800 13/2 +
11 0.35000 9/2 - *
12 0.36577 5/2 -
13 0.42793 5/2 -
14 0.43872 3/2 -
15 0.44422 7/2 +
16 0.49879 3/2 -
17 0.50585 3/2 -
18 0.53154 5/2 -
19 0.55003 3/2 -
20 0.55735 3/2 -
21 0.56269 9/2 -
22 0.59490 11/2 - *
23 0.59963 3/2 -
24 0.62201 3/2 +
25 0.63060 9/2 -
26 0.63420 5/2 -
27 0.66740 1/2 -
28 0.67213 5/2 -
29 0.67310 5/2 -
30 0.67990 3/2 -
31 0.68842 1/2 -
32 0.71690 5/2 -
33 0.71699 5/2 -
34 0.73550 3/2 -
-------------------
*) Coupled levels in CC calculation
Table 2. Level density parameters
--------------------------------------------------------
Nuclide a* Pair Eshell T E0 Ematch
1/MeV MeV MeV MeV MeV MeV
--------------------------------------------------------
Os-190 23.1000 1.7411 0.3025 0.5036 -0.0238 6.0343
Os-189 23.6000 0.8729 0.7207 0.5092 -1.1969 5.5241
Os-188 23.1000 1.7504 0.7049 0.4799 0.1757 5.6719
Os-187 22.9000 0.8775 0.9894 0.5173 -1.2331 5.5812
Re-189 21.1918 0.8729 0.9313 0.5028 -0.6533 4.8062
Re-188 22.0000 0.0000 0.8388 0.4802 -1.4013 3.6931
Re-187 20.9976 0.8775 1.0287 0.5196 -0.8390 5.1039
Re-186 21.4000 0.0000 0.9320 0.4744 -1.2480 3.4655
Re-185 20.8032 0.8823 1.1055 0.4981 -0.5577 4.6703
W-188 21.9779 1.7504 1.2256 0.5151 -0.1841 6.2107
W-187 23.5700 0.8775 1.1868 0.4614 -0.6754 4.6629
W-186 23.1400 1.7598 1.2307 0.4935 -0.1424 6.0929
W-185 22.7200 0.8823 1.2247 0.4842 -0.8101 4.9225
W-184 22.1100 1.7693 1.2350 0.5106 -0.1439 6.1796
W-183 21.5000 0.8871 1.1150 0.5015 -0.7444 4.9247
W-182 21.6000 1.7790 1.2320 0.4968 0.1520 5.7824
--------------------------------------------------------
Table 3. Gamma-ray strength function for Os-190
--------------------------------------------------------
K0 = 1.700 E0 = 4.500 (MeV)
* E1: ER = 12.68 (MeV) EG = 2.60 (MeV) SIG = 206.00 (mb)
ER = 14.40 (MeV) EG = 4.16 (MeV) SIG = 401.00 (mb)
ER = 5.50 (MeV) EG = 0.60 (MeV) SIG = 6.50 (mb)
ER = 1.90 (MeV) EG = 0.50 (MeV) SIG = 0.06 (mb)
* M1: ER = 7.13 (MeV) EG = 4.00 (MeV) SIG = 1.33 (mb)
* E2: ER = 10.96 (MeV) EG = 3.83 (MeV) SIG = 4.73 (mb)
--------------------------------------------------------
References
1) Mughabghab,S.F.: "Atlas of Neutron Resonances, Fifth
Edition: Resonance Parameters and Thermal Cross Sections.
Z=1-100", Elsevier Science (2006).
2) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)
[in Japanese].
3) Iwamoto,O.: JAERI-Data/Code 2003-020 (2003).
4) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).
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).
15) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990).
16) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).