66-Dy-161 JAEA EVAL-Nov09 N.Iwamoto,S.Chiba
DIST-MAY10 20100119
----JENDL-4.0 MATERIAL 6640
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
History
09-11 The resolved resonance parameters were evaluated by
S.Chiba.
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 400 eV
The evaluation is based on the work of Mughabghab /1/
A scattering radius of 7.9 fm was used.
Unresolved resonance region : 400.0 eV - 100.0 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
OPTMAN /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 6.1772e+02
Elastic 1.7604e+01
n,gamma 6.0011e+02 1.0886e+03
n,alpha 6.7247e-04
----------------------------------------------------------
(*) 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: 0,2,4,7,10,14,20,37 (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/
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 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 Dy-161
-------------------
No. Ex(MeV) J PI
-------------------
0 0.00000 5/2 + *
1 0.02565 5/2 -
2 0.04382 7/2 + *
3 0.07457 3/2 -
4 0.10040 9/2 + *
5 0.10306 7/2 -
6 0.13176 5/2 -
7 0.18423 11/2 + *
8 0.20109 9/2 -
9 0.21295 7/2 -
10 0.26744 13/2 + *
11 0.31494 9/2 -
12 0.32069 11/2 -
13 0.36697 1/2 -
14 0.40699 15/2 + *
15 0.41823 3/2 -
16 0.44340 11/2 -
17 0.45143 5/2 -
18 0.45723 13/2 -
19 0.48556 11/2 -
20 0.50810 17/2 + *
21 0.51200 9/2 -
22 0.52100 1/2 -
23 0.53420 5/2 -
24 0.55025 3/2 +
25 0.56794 7/2 -
26 0.58710 13/2 -
27 0.60758 1/2 +
28 0.60983 5/2 +
29 0.62823 9/2 -
30 0.63317 5/2 +
31 0.64200 11/2 -
32 0.67832 3/2 +
33 0.68830 9/2 +
34 0.69608 7/2 +
35 0.69914 3/2 +
36 0.71705 9/2 -
37 0.71860 19/2 + *
38 0.73091 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
--------------------------------------------------------
Dy-162 19.5000 1.8856 2.4639 0.5582 -0.4126 6.7742
Dy-161 20.0000 0.9457 2.7684 0.5468 -1.4246 5.8432
Dy-160 21.1000 1.8974 2.8705 0.5085 -0.2487 6.3915
Dy-159 19.1000 0.9517 3.1578 0.5560 -1.4112 5.8333
Tb-161 18.4519 0.9457 2.4950 0.5607 -1.0970 5.5427
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
Gd-160 19.1372 1.8974 2.4922 0.5804 -0.6190 7.1078
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
Gd-155 20.5000 0.9639 3.7045 0.5229 -1.4800 5.7609
--------------------------------------------------------
Table 3. Gamma-ray strength function for Dy-162
--------------------------------------------------------
* E1: ER = 12.25 (MeV) EG = 3.11 (MeV) SIG = 138.31 (mb)
ER = 16.04 (MeV) EG = 5.21 (MeV) SIG = 276.62 (mb)
ER = 6.20 (MeV) EG = 4.50 (MeV) SIG = 1.10 (mb)
ER = 3.10 (MeV) EG = 1.50 (MeV) SIG = 0.60 (mb)
* M1: ER = 7.52 (MeV) EG = 4.00 (MeV) SIG = 0.96 (mb)
* E2: ER = 11.56 (MeV) EG = 4.17 (MeV) SIG = 3.84 (mb)
--------------------------------------------------------
References
1) Mughabghab, S.F.: "Neutron Cross Sections, Vol. 1, Neutron
Resonance Parameters and Thermal Cross Sections, Part B",
Academic Press (1984).
2) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)
[in Japanese].
3) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004).
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).