65-Tb-159 JAEA+ EVAL-Dec09 N.Iwamoto,A.Zukeran
DIST-MAY10 20100119
----JENDL-4.0 MATERIAL 6525
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
History
09-12 The resolved resonance parameters were evaluated by
A.Zukeran.
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 (MLBW formula): below 1.188keV
In the JENDL-2 evaluation, resonance parameters were mainly
taken from the experimental data by Ohkubo and Kawarasaki
/1/ and by Derrien and Alix/2/. The average radiation
width was assumed to be 0.097 eV. A negative resonance was
added at -0.1 eV so as to reproduce the capture cross
section of 25.5+-1.1 barns and the elastic scattering of
20+-2 barns at 0.0253 eV/3/. Scattering radius of 8.3 fm
was taken from the recommendation by Mughabghab and Garber
/3/.
In JENDL-4, the data for 3.36 - 14.5 eV were replaced with
the ones obtained by Vertebnyj et al./4/ The parameters
for the negative resonance were re-adjusted. The scattering
radius was changed to 7.8 fm.
Unresolved resonance region : 1.188 keV - 130.0 keV
The unresolved resonance paramters (URP) were determined by
ASREP code /5/ so as to reproduce the evaluated total and
capture cross sections calculated with optical model code
OPTMAN /6/ and CCONE /7/. 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 3.0033e+01
Elastic 6.8988e+00
n,gamma 2.3134e+01 4.0913e+02
n,alpha 2.1716e-09
----------------------------------------------------------
(*) 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 /7/.
MT= 16 (n,2n) cross section
Calculated with CCONE code /7/.
MT= 17 (n,3n) cross section
Calculated with CCONE code /7/.
MT= 22 (n,na) cross section
Calculated with CCONE code /7/.
MT= 28 (n,np) cross section
Calculated with CCONE code /7/.
MT= 32 (n,nd) cross section
Calculated with CCONE code /7/.
MT= 33 (n,nt) cross section
Calculated with CCONE code /7/.
MT= 41 (n,2np) cross section
Calculated with CCONE code /7/.
MT= 51-91 (n,n') cross section
Calculated with CCONE code /7/.
MT=102 Capture cross section
Calculated with CCONE code /7/.
MT=103 (n,p) cross section
Calculated with CCONE code /7/.
MT=104 (n,d) cross section
Calculated with CCONE code /7/.
MT=105 (n,t) cross section
Calculated with CCONE code /7/.
MT=106 (n,He3) cross section
Calculated with CCONE code /7/.
MT=107 (n,a) cross section
Calculated with CCONE code /7/.
MF= 4 Angular distributions of emitted neutrons
MT= 2 Elastic scattering
Calculated with CCONE code /7/.
MF= 6 Energy-angle distributions of emitted particles
MT= 16 (n,2n) reaction
Calculated with CCONE code /7/.
MT= 17 (n,3n) reaction
Calculated with CCONE code /7/.
MT= 22 (n,na) reaction
Calculated with CCONE code /7/.
MT= 28 (n,np) reaction
Calculated with CCONE code /7/.
MT= 32 (n,nd) reaction
Calculated with CCONE code /7/.
MT= 33 (n,nt) reaction
Calculated with CCONE code /7/.
MT= 41 (n,2np) reaction
Calculated with CCONE code /7/.
MT= 51-91 (n,n') reaction
Calculated with CCONE code /7/.
MT=102 Capture reaction
Calculated with CCONE code /7/.
*****************************************************************
Nuclear Model Calculation with CCONE code /7/
*****************************************************************
Models and parameters used in the CCONE calculation
1) Optical model
* coupled channels calculation
coupled levels: 0,1,2,3,5,10,17 (see Table 1)
* optical model potential
neutron omp: Kunieda,S. et al./8/ (+)
proton omp: Koning,A.J. and Delaroche,J.P./9/ (+)
deuteron omp: Lohr,J.M. and Haeberli,W./10/
triton omp: Becchetti Jr.,F.D. and Greenlees,G.W./11/
He3 omp: Becchetti Jr.,F.D. and Greenlees,G.W./11/
alpha omp: McFadden,L. and Satchler,G.R./12/ (+)
(+) omp parameters were modified.
2) Two-component exciton model/13/
* Global parametrization of Koning-Duijvestijn/14/
was used.
* Gamma emission channel/15/ was added to simulate direct
and semi-direct capture reaction.
3) Hauser-Feshbach statistical model
* Width fluctuation correction/16/ 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/17/.
Parameters are shown in Table 2.
* Gamma-ray strength function of enhanced generalized
Lorentzian form/18/,/19/ 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 Tb-159
-------------------
No. Ex(MeV) J PI
-------------------
0 0.00000 3/2 + *
1 0.05800 5/2 + *
2 0.13750 7/2 + *
3 0.24115 9/2 + *
4 0.34828 5/2 +
5 0.36205 11/2 + *
6 0.36355 5/2 -
7 0.38840 7/2 -
8 0.42820 7/2 +
9 0.45460 9/2 -
10 0.51040 13/2 + *
11 0.53200 9/2 +
12 0.53670 7/2 +
13 0.54510 11/2 -
14 0.54760 7/2 -
15 0.58081 1/2 +
16 0.61762 3/2 +
17 0.66891 15/2 + *
18 0.67424 5/2 +
19 0.67790 9/2 -
20 0.76130 7/2 +
21 0.77710 7/2 +
22 0.79900 15/2 -
23 0.82220 11/2 -
24 0.85496 1/2 -
25 0.85730 9/2 +
-------------------
*) Coupled levels in CC calculation
Table 2. Level density parameters
--------------------------------------------------------
Nuclide a* Pair Eshell T E0 Ematch
1/MeV MeV MeV MeV MeV MeV
--------------------------------------------------------
Tb-160 18.9000 0.0000 2.5855 0.5446 -1.9885 4.4661
Tb-159 21.0000 0.9517 2.9024 0.4767 -0.7563 4.8234
Tb-158 19.3000 0.0000 3.0376 0.4617 -1.2200 3.2269
Tb-157 18.0565 0.9577 3.3696 0.5538 -1.1365 5.5068
Gd-159 19.9000 0.9517 2.6302 0.5300 -1.1252 5.4620
Gd-158 19.3000 1.9093 2.8152 0.5596 -0.4648 6.8458
Gd-157 20.0000 0.9577 3.0516 0.5315 -1.2892 5.6268
Gd-156 19.0000 1.9215 3.2702 0.5513 -0.3880 6.7098
Eu-158 18.8084 0.0000 2.4374 0.4933 -1.3276 3.5000
Eu-157 18.0565 0.9577 2.7904 0.5507 -0.9395 5.3155
Eu-156 18.0000 0.0000 2.8275 0.5361 -1.7176 4.0906
Eu-155 17.9000 0.9639 3.3259 0.5676 -1.2578 5.7030
Eu-154 19.2000 0.0000 3.6717 0.5485 -2.4486 4.8922
Eu-153 17.3400 0.9701 3.8805 0.5963 -1.6297 6.1695
--------------------------------------------------------
Table 3. Gamma-ray strength function for Tb-160
--------------------------------------------------------
K0 = 1.900 E0 = 4.500 (MeV)
* E1: ER = 12.22 (MeV) EG = 2.34 (MeV) SIG = 160.00 (mb)
ER = 15.67 (MeV) EG = 4.97 (MeV) SIG = 220.00 (mb)
ER = 5.60 (MeV) EG = 1.80 (MeV) SIG = 5.00 (mb)
ER = 3.00 (MeV) EG = 1.50 (MeV) SIG = 0.60 (mb)
* M1: ER = 7.55 (MeV) EG = 4.00 (MeV) SIG = 1.37 (mb)
* E2: ER = 11.60 (MeV) EG = 4.19 (MeV) SIG = 3.75 (mb)
--------------------------------------------------------
References
1) Ohkubo, M. and Kawarasaki, Y.: JAERI-M 7545 (1978).
2) Derrien, H. and Alix, M.: CEA-N-1867 (1975).
3) Mughabghab, S.F. and Garber, D.I.: "Neutron Cross Sections,
Vol. 1, Resonance Parameters", BNL 325, 3rd ed., Vol. 1,
(1973).
4) Vertebnyj, V.P. et al.: 83 Kiev, 3, 37 (1983).
5) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)
[in Japanese].
6) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004).
7) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).
8) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).
9) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)
[Global potential].
10) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).
11) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.
J.H.Williams Lab., Univ. Minnesota (1969).
12) McFadden,L. and Satchler,G.R.: Nucl. Phys. 84, 177 (1966).
13) Kalbach,C.: Phys. Rev. C33, 818 (1986).
14) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).
15) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).
16) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).
17) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151
(1994).
18) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990).
19) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).