50-Sn-122
50-Sn-122 JAEA EVAL-Dec09 N.Iwamoto,K.Shibata
DIST-MAY10 20100119
----JENDL-4.0 MATERIAL 5055
-----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 80 keV
In JENDL-3.3, resonance energies and neutron widths were
based on mainly the data measured by Nakajima et al./1/
and partially those given by Mughabghab et al./2/ Neutron
orbital angular momentum L of some resonances was estimated
with a method of Bollinger and Thomas/4/. Averaged
radiation width of 130 meV was assumed from the systematics
of measured values for neighboring nuclides. Scattering
radius was taken as 5.7 fm /2/. A negative resonance was
added so as to reproduce the thermal capture cross section
given by Mughabghab et al.
In JENDL-4, the data above 13.2 keV were replaced with the
ones obtained by Carlton et al./3/ A value of 130 meV
was assumed for the radiation width. The upper boudary
was extended to 80 keV.
Unresolved resonance region : 80 keV - 200 keV
The unresolved resonance paramters (URP) were determined by
ASREP code /4/ so as to reproduce the evaluated total and
capture cross sections calculated with optical model code
OPTMAN /5/ and CCONE /6/. 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 3.8570e+00
Elastic 3.7174e+00
n,gamma 1.3959e-01 9.5440e-01
----------------------------------------------------------
(*) 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 /6/.
MT= 16 (n,2n) cross section
Calculated with CCONE code /6/.
MT= 17 (n,3n) cross section
Calculated with CCONE code /6/.
MT= 22 (n,na) cross section
Calculated with CCONE code /6/.
MT= 28 (n,np) cross section
Calculated with CCONE code /6/.
MT= 51-91 (n,n') cross section
Calculated with CCONE code /6/.
MT=102 Capture cross section
Calculated with CCONE code /6/.
MT=103 (n,p) cross section
Calculated with CCONE code /6/.
MT=104 (n,d) cross section
Calculated with CCONE code /6/.
MT=105 (n,t) cross section
Calculated with CCONE code /6/.
MT=106 (n,He3) cross section
Calculated with CCONE code /6/.
MT=107 (n,a) cross section
Calculated with CCONE code /6/.
MF= 4 Angular distributions of emitted neutrons
MT= 2 Elastic scattering
Calculated with CCONE code /6/.
MF= 6 Energy-angle distributions of emitted particles
MT= 16 (n,2n) reaction
Calculated with CCONE code /6/.
MT= 17 (n,3n) reaction
Calculated with CCONE code /6/.
MT= 22 (n,na) reaction
Calculated with CCONE code /6/.
MT= 28 (n,np) reaction
Calculated with CCONE code /6/.
MT= 51-91 (n,n') reaction
Calculated with CCONE code /6/.
MT=102 Capture reaction
Calculated with CCONE code /6/.
*****************************************************************
Nuclear Model Calculation with CCONE code /6/
*****************************************************************
Models and parameters used in the CCONE calculation
1) Optical model
* coupled channels calculation
coupled levels: 0,1,9 (see Table 1)
* optical model potential
neutron omp: Kunieda,S. et al./7/ (+)
proton omp: Kunieda,S. et al./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 Sn-122
-------------------
No. Ex(MeV) J PI
-------------------
0 0.00000 0 + *
1 1.14051 2 + *
2 2.08771 0 +
3 2.14206 4 +
4 2.15381 2 +
5 2.24581 5 -
6 2.33109 4 +
7 2.40903 7 -
8 2.41554 2 +
9 2.49267 3 - *
10 2.53033 0 +
11 2.55542 6 +
12 2.65137 5 -
13 2.65300 6 -
14 2.65700 3 +
15 2.67557 0 +
16 2.69004 8 +
17 2.73450 2 +
18 2.75101 5 -
19 2.76560 10 +
20 2.77555 2 +
21 2.83788 6 -
22 2.85547 4 -
23 2.86773 3 -
24 2.87979 2 +
25 2.94496 3 +
26 2.95912 4 +
27 2.97110 1 +
28 2.97339 4 +
-------------------
*) Coupled levels in CC calculation
Table 2. Level density parameters
--------------------------------------------------------
Nuclide a* Pair Eshell T E0 Ematch
1/MeV MeV MeV MeV MeV MeV
--------------------------------------------------------
Sn-123 15.9572 1.0820 -0.0224 0.6542 -0.5670 5.7354
Sn-122 15.1883 2.1729 0.1587 0.6646 0.6099 6.7179
Sn-121 14.9000 1.0909 0.9681 0.6514 -0.5137 5.5290
Sn-120 14.7000 2.1909 0.8820 0.6695 0.4967 6.8161
In-122 15.1132 0.0000 0.9721 0.6133 -1.2958 3.9041
In-121 14.4439 1.0909 1.3854 0.6275 -0.2553 5.0642
In-120 14.9043 0.0000 1.9246 0.6079 -1.4610 4.0000
In-119 14.2400 1.1000 2.1477 0.6266 -0.3980 5.1833
Cd-121 15.7486 1.0909 1.5385 0.6783 -1.3360 6.5598
Cd-120 14.9768 2.1909 1.6826 0.6507 0.3296 6.8575
Cd-119 15.5394 1.1000 2.5578 0.6443 -1.1874 6.1408
Cd-118 14.7649 2.2094 2.3367 0.6412 0.3136 6.8030
Cd-117 16.7000 1.1094 2.9235 0.6001 -1.1587 5.9328
--------------------------------------------------------
Table 3. Gamma-ray strength function for Sn-123
--------------------------------------------------------
* E1: ER = 15.51 (MeV) EG = 4.88 (MeV) SIG = 278.46 (mb)
* M1: ER = 8.24 (MeV) EG = 4.00 (MeV) SIG = 0.66 (mb)
* E2: ER = 12.67 (MeV) EG = 4.63 (MeV) SIG = 2.61 (mb)
--------------------------------------------------------
References
1) Nakajima, Y. et al.: Ann. Nucl. Energy, 17, 95 (1990).
2) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I,
Part A", Academic Press (1981).
3) Carlton, R.F. et al.: Phys. Rev., C52, 1498 (1995).
4) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)
[in Japanese].
5) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004).
6) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).
7) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).
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).