66-Dy-163 JAEA EVAL-Nov09 N.Iwamoto,S.Chiba
DIST-MAY10 20100119
----JENDL-4.0 MATERIAL 6646
-----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 1.003 keV
The evaluation is based on the work of Mughabghab /1/
A scattering radius of 7.5 fm was used.
Unresolved resonance region : 1.003 keV - 160.0 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 1.2753e+02
Elastic 3.3418e+00
n,gamma 1.2419e+02 1.4908e+03
n,alpha 4.7968e-06
----------------------------------------------------------
(*) 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: 0,1,2,4,10,19,30 (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-163
-------------------
No. Ex(MeV) J PI
-------------------
0 0.00000 5/2 - *
1 0.07344 7/2 - *
2 0.16734 9/2 - *
3 0.25089 5/2 +
4 0.28157 11/2 - *
5 0.28559 7/2 +
6 0.33654 9/2 +
7 0.35115 1/2 -
8 0.38975 3/2 -
9 0.41238 11/2 +
10 0.41524 13/2 - *
11 0.42184 3/2 -
12 0.42768 5/2 -
13 0.45000 7/2 -
14 0.47539 5/2 -
15 0.49720 13/2 +
16 0.51455 7/2 -
17 0.55302 7/2 -
18 0.56600 7/2 -
19 0.56871 15/2 - *
20 0.58793 9/2 -
21 0.61200 1/2 -
22 0.64625 9/2 -
23 0.66000 3/2 +
24 0.70500 1/2 -
25 0.71147 5/2 -
26 0.71200 5/2 +
27 0.71827 11/2 -
28 0.72760 9/2 -
29 0.73766 1/2 +
30 0.74000 17/2 - *
31 0.76621 3/2 +
32 0.78110 5/2 +
33 0.79339 1/2 -
34 0.80131 7/2 -
35 0.82080 3/2 -
36 0.82680 9/2 +
37 0.85112 7/2 +
38 0.85929 3/2 +
39 0.88301 5/2 -
40 0.88429 1/2 +
-------------------
*) 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-164 19.6000 1.8741 2.0177 0.5619 -0.3641 6.7556
Dy-163 19.9000 0.9399 2.1664 0.5502 -1.2684 5.7265
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
Tb-163 18.6492 0.9399 2.1299 0.5457 -0.8637 5.2359
Tb-162 18.6000 0.0000 1.8944 0.4625 -0.8591 2.8270
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
Gd-162 19.3418 1.8856 2.3374 0.5664 -0.4417 6.8501
Gd-161 19.6000 0.9457 2.2447 0.5241 -0.8691 5.1638
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
--------------------------------------------------------
Table 3. Gamma-ray strength function for Dy-164
--------------------------------------------------------
* E1: ER = 12.14 (MeV) EG = 3.06 (MeV) SIG = 140.23 (mb)
ER = 16.06 (MeV) EG = 5.22 (MeV) SIG = 280.47 (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 = 7.49 (MeV) EG = 4.00 (MeV) SIG = 0.97 (mb)
* E2: ER = 11.51 (MeV) EG = 4.14 (MeV) SIG = 3.82 (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).