46-Pd-110 JAEA EVAL-Dec09 N.Iwamoto,K.Shibata
DIST-MAY10 20100119
----JENDL-4.0 MATERIAL 4649
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
History
09-12 The resolved resonance parameters were evaluated by
K.Shibata.
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 8 keV
In JENDL-3.3, resonance parameters were mainly taken from
the recommendation by Mughabghab et al./1/ Average
radiation width of 60 meV/1/ was assumed. A negative
resonance was added at -20 eV so as to reproduce the thermal
capture cross sections given by Mughabghab et al.
In JENDL-4, the data for 5.19 - 1.4 keV were replaced with
the ones obtained by Smith et al./2/ A values of 60 meV
was used for unknown radiation withds. Spin of the p-wave
resonance was determined from the spin distribution of
level density randomly.
Unresolved resonance region : 8 keV - 150 keV
The unresolved resonance paramters (URP) were determined by
ASREP code /3/ so as to reproduce the evaluated total and
capture cross sections calculated with optical model code
OPTMAN /4/ and CCONE /5/. 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 5.2444e+00
Elastic 5.0188e+00
n,gamma 2.2560e-01 3.2840e+00
----------------------------------------------------------
(*) 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 /5/.
MT= 16 (n,2n) cross section
Calculated with CCONE code /5/.
MT= 17 (n,3n) cross section
Calculated with CCONE code /5/.
MT= 22 (n,na) cross section
Calculated with CCONE code /5/.
MT= 28 (n,np) cross section
Calculated with CCONE code /5/.
MT= 51-91 (n,n') cross section
Calculated with CCONE code /5/.
MT=102 Capture cross section
Calculated with CCONE code /5/.
MT=103 (n,p) cross section
Calculated with CCONE code /5/.
MT=104 (n,d) cross section
Calculated with CCONE code /5/.
MT=105 (n,t) cross section
Calculated with CCONE code /5/.
MT=106 (n,He3) cross section
Calculated with CCONE code /5/.
MT=107 (n,a) cross section
Calculated with CCONE code /5/.
MF= 4 Angular distributions of emitted neutrons
MT= 2 Elastic scattering
Calculated with CCONE code /5/.
MF= 6 Energy-angle distributions of emitted particles
MT= 16 (n,2n) reaction
Calculated with CCONE code /5/.
MT= 17 (n,3n) reaction
Calculated with CCONE code /5/.
MT= 22 (n,na) reaction
Calculated with CCONE code /5/.
MT= 28 (n,np) reaction
Calculated with CCONE code /5/.
MT= 51-91 (n,n') reaction
Calculated with CCONE code /5/.
MT=102 Capture reaction
Calculated with CCONE code /5/.
*****************************************************************
Nuclear Model Calculation with CCONE code /5/
*****************************************************************
Models and parameters used in the CCONE calculation
1) Optical model
* coupled channels calculation
coupled levels: 0,1,3,10,22 (see Table 1)
* optical model potential
neutron omp: Kunieda,S. et al./6/ (+)
proton omp: Koning,A.J. and Delaroche,J.P./7/
deuteron omp: Lohr,J.M. and Haeberli,W./8/
triton omp: Becchetti Jr.,F.D. and Greenlees,G.W./9/
He3 omp: Becchetti Jr.,F.D. and Greenlees,G.W./9/
alpha omp: Huizenga,J.R. and Igo,G./10/
(+) omp parameters were modified.
2) Two-component exciton model/11/
* Global parametrization of Koning-Duijvestijn/12/
was used.
* Gamma emission channel/13/ was added to simulate direct
and semi-direct capture reaction.
3) Hauser-Feshbach statistical model
* Width fluctuation correction/14/ 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/15/.
Parameters are shown in Table 2.
* Gamma-ray strength function of generalized Lorentzian form
/16/,/17/ 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 Pd-110
-------------------
No. Ex(MeV) J PI
-------------------
0 0.00000 0 + *
1 0.37380 2 + *
2 0.81361 2 +
3 0.92077 4 + *
4 0.94673 0 +
5 1.17066 0 +
6 1.21224 3 +
7 1.21442 2 +
8 1.39824 4 +
9 1.47007 2 +
10 1.57404 6 + *
11 1.58400 0 +
12 1.64100 0 +
13 1.71906 4 +
14 1.85800 2 +
15 1.86400 2 +
16 1.88967 2 +
17 1.90018 2 +
18 1.93447 4 +
19 1.95600 4 +
20 1.98800 4 +
21 2.01500 4 +
22 2.03767 3 - *
23 2.06100 6 +
24 2.08900 4 +
25 2.09500 0 +
26 2.12530 1 -
27 2.14000 2 +
28 2.14170 4 +
29 2.19300 2 -
30 2.19400 6 +
31 2.25900 0 +
32 2.27610 3 -
33 2.29330 5 -
34 2.29500 4 +
35 2.29600 8 +
36 2.32206 4 +
37 2.33200 6 +
38 2.36970 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
--------------------------------------------------------
Pd-111 15.9000 1.1390 4.1515 0.6121 -1.4174 6.1649
Pd-110 13.9128 2.2883 3.6344 0.6741 -0.1028 7.3768
Pd-109 16.0000 1.1494 3.8267 0.6463 -1.8210 6.7457
Pd-108 14.3000 2.3094 3.1785 0.6359 0.3436 6.8413
Rh-110 14.6000 0.0000 4.3454 0.5233 -1.1899 3.2077
Rh-109 13.2140 1.1494 4.3457 0.6878 -1.3307 6.2934
Rh-108 15.6000 0.0000 4.1884 0.5114 -1.3068 3.3132
Rh-107 13.0075 1.1601 4.0295 0.7116 -1.4170 6.5036
Ru-109 14.4845 1.1494 4.6016 0.6919 -2.0708 7.0469
Ru-108 13.6986 2.3094 4.4330 0.6832 -0.3716 7.6387
Ru-107 15.5000 1.1601 4.4476 0.6172 -1.4266 6.1858
Ru-106 13.4840 2.3311 4.1609 0.6686 0.0022 7.2594
Ru-105 15.3000 1.1711 4.2450 0.6623 -1.8991 6.8479
--------------------------------------------------------
Table 3. Gamma-ray strength function for Pd-111
--------------------------------------------------------
* E1: ER = 15.92 (MeV) EG = 7.18 (MeV) SIG = 199.00 (mb)
* M1: ER = 8.53 (MeV) EG = 4.00 (MeV) SIG = 1.09 (mb)
* E2: ER = 13.11 (MeV) EG = 4.78 (MeV) SIG = 2.38 (mb)
--------------------------------------------------------
References
1) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I,
Part A", Academic Press (1981).
2) Smith, D.A. et al.: Phys. Rev., C65, 024607 (2002).
3) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)
[in Japanese].
4) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004).
5) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).
6) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).
7) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)
[Global potential].
8) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).
9) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.
J.H.Williams Lab., Univ. Minnesota (1969).
10) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962).
11) Kalbach,C.: Phys. Rev. C33, 818 (1986).
12) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).
13) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).
14) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).
15) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151
(1994).
16) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990).
17) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).