76-Os-192 JAEA EVAL-Jan10 N.Iwamoto
DIST-MAY10 20100121
----JENDL-4.0 MATERIAL 7649
-----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 240 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 : 240 eV - 200 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 1.8060e+01
Elastic 1.4942e+01
n,gamma 3.1174e+00 1.0259e+01
n,alpha 1.2102e-15
----------------------------------------------------------
(*) 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= 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= 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: 0,1,3,8,23 (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-192
-------------------
No. Ex(MeV) J PI
-------------------
0 0.00000 0 + *
1 0.20579 2 + *
2 0.48906 2 +
3 0.58028 4 + *
4 0.69037 3 +
5 0.90959 4 +
6 0.95654 0 +
7 1.06954 4 +
8 1.08923 6 + *
9 1.12751 2 +
10 1.14352 5 +
11 1.20629 0 +
12 1.34115 3 -
13 1.36202 5 +
14 1.40986 2 +
15 1.45031 2 +
16 1.45660 4 +
17 1.46534 6 +
18 1.56060 4 -
19 1.59174 3 +
20 1.61287 2 +
21 1.64510 6 +
22 1.66509 2 +
23 1.70839 8 + *
24 1.71291 7 +
25 1.73379 2 +
26 1.78034 3 +
27 1.80771 2 +
28 1.82651 1 -
29 1.83740 2 +
30 1.85797 3 +
31 1.86787 2 +
32 1.86870 2 -
33 1.87879 2 +
34 1.89493 3 +
35 1.90268 0 +
36 1.92168 0 +
37 1.92400 0 +
38 1.93690 2 +
39 1.94000 4 +
40 1.94080 0 +
-------------------
*) 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-193 24.8000 0.8638 -0.6182 0.4975 -0.8915 5.2162
Os-192 22.3797 1.7321 -0.3439 0.5319 -0.0502 6.2330
Os-191 24.1000 0.8683 0.1619 0.5157 -1.2338 5.6493
Os-190 23.1000 1.7411 0.3025 0.5036 -0.0238 6.0343
Re-192 22.2067 0.0000 0.2223 0.3842 -0.4006 2.0000
Re-191 21.3859 0.8683 0.5919 0.5198 -0.8133 5.0956
Re-190 22.0088 0.0000 0.6386 0.3818 -0.4260 2.0158
Re-189 21.1918 0.8729 0.9313 0.5028 -0.6533 4.8062
W-191 22.7810 0.8683 1.0433 0.2918 0.8686 1.8683
W-190 22.1789 1.7411 1.1218 0.2965 1.7487 2.7411
W-189 22.5864 0.8729 1.4546 0.4721 -0.6930 4.7000
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
--------------------------------------------------------
Table 3. Gamma-ray strength function for Os-193
--------------------------------------------------------
K0 = 1.700 E0 = 4.500 (MeV)
* E1: ER = 12.68 (MeV) EG = 2.49 (MeV) SIG = 206.00 (mb)
ER = 14.35 (MeV) EG = 4.41 (MeV) SIG = 389.00 (mb)
ER = 5.50 (MeV) EG = 1.10 (MeV) SIG = 2.50 (mb)
ER = 1.60 (MeV) EG = 0.30 (MeV) SIG = 0.03 (mb)
* M1: ER = 7.09 (MeV) EG = 4.00 (MeV) SIG = 1.37 (mb)
* E2: ER = 10.90 (MeV) EG = 3.79 (MeV) SIG = 4.70 (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).