55-Cs-135 JAEA+ EVAL-Apr09 N.Iwamoto,H.Matsunobu
DIST-MAY10 20100119
----JENDL-4.0 MATERIAL 5531
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
History
09-04 The resolved resonance parameters were evaluated by
H.Matsunobu.
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 230 eV
Resonance parameters of JENDL-3.3 were revised as follows :
The resonance energies and neutron widths of 6 levels, and
radiation width of the second level (42.2 ev) which were
measured by Anufriev et al./1/ were adopted. the rdiation
widths of the remaining 5 levels and a negative level were
assumed to be 175 meV. The values of total j for the
negative and positive 6 levels were estimated by random
number method. The neutron width of the negative level was
adjusted so as to reproduce the thermal capture cross
section of 8.3+-0.3 barns at 0.0253 eV measured by Katoh
et al./2/
Unresolved resonance region : 230 eV - 160 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 1.3143e+01
Elastic 4.8408e+00
n,gamma 8.3019e+00 5.3519e+01
n,alpha 1.2909e-14
----------------------------------------------------------
(*) 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= 24 (n,2na) cross section
Calculated with CCONE code /5/.
MT= 28 (n,np) cross section
Calculated with CCONE code /5/.
MT= 29 (n,n2a) cross section
Calculated with CCONE code /5/.
MT= 30 (n,2n2a) cross section
Calculated with CCONE code /5/.
MT= 32 (n,nd) cross section
Calculated with CCONE code /5/.
MT= 33 (n,nt) cross section
Calculated with CCONE code /5/.
MT= 34 (n,nHe3) cross section
Calculated with CCONE code /5/.
MT= 41 (n,2np) cross section
Calculated with CCONE code /5/.
MT= 44 (n,n2p) cross section
Calculated with CCONE code /5/.
MT= 45 (n,npa) 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/.
MT=108 (n,2a) cross section
Calculated with CCONE code /5/.
MT=111 (n,2p) cross section
Calculated with CCONE code /5/.
MT=112 (n,pa) cross section
Calculated with CCONE code /5/.
MT=115 (n,pd) cross section
Calculated with CCONE code /5/.
MT=116 (n,pt) cross section
Calculated with CCONE code /5/.
MT=117 (n,da) 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= 24 (n,2na) reaction
Calculated with CCONE code /5/.
MT= 28 (n,np) reaction
Calculated with CCONE code /5/.
MT= 29 (n,n2a) reaction
Calculated with CCONE code /5/.
MT= 30 (n,2n2a) reaction
Calculated with CCONE code /5/.
MT= 32 (n,nd) reaction
Calculated with CCONE code /5/.
MT= 33 (n,nt) reaction
Calculated with CCONE code /5/.
MT= 34 (n,nHe3) reaction
Calculated with CCONE code /5/.
MT= 41 (n,2np) reaction
Calculated with CCONE code /5/.
MT= 44 (n,n2p) reaction
Calculated with CCONE code /5/.
MT= 45 (n,npa) 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
* 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: McFadden,L. and Satchler,G.R./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 Cs-135
-------------------
No. Ex(MeV) J PI
-------------------
0 0.00000 7/2 +
1 0.24977 5/2 +
2 0.40803 1/2 +
3 0.60815 5/2 +
4 0.78684 11/2 +
5 0.98140 1/2 +
6 1.06239 1/2 +
-------------------
Table 2. Level density parameters
--------------------------------------------------------
Nuclide a* Pair Eshell T E0 Ematch
1/MeV MeV MeV MeV MeV MeV
--------------------------------------------------------
Cs-136 18.0000 0.0000 -2.9176 0.6768 -1.3925 5.0000
Cs-135 16.6000 1.0328 -1.8144 0.6675 -0.2856 5.6078
Cs-134 17.0000 0.0000 -0.8946 0.7066 -2.2698 5.8956
Cs-133 16.4429 1.0405 -0.1729 0.7096 -1.3562 6.9453
Xe-135 20.2000 1.0328 -3.8043 0.5665 0.4707 4.2857
Xe-134 17.1069 2.0733 -2.8193 0.7693 -0.1097 8.7590
Xe-133 18.7000 1.0405 -1.7673 0.6413 -0.6524 6.0509
Xe-132 16.8500 2.0889 -1.1507 0.6595 0.5201 6.8662
I-134 16.8488 0.0000 -4.8096 0.8747 -2.2475 8.6722
I-133 16.1297 1.0405 -3.5913 0.8275 -1.0073 8.1906
I-132 16.6361 0.0000 -2.4976 0.7769 -2.2437 6.6852
I-131 15.9219 1.0484 -1.6425 0.7356 -0.8231 6.6968
I-130 16.4000 0.0000 -0.6800 0.8536 -4.2325 9.0264
I-129 15.7137 1.0565 -0.1025 0.6848 -0.7998 6.1306
--------------------------------------------------------
Table 3. Gamma-ray strength function for Cs-136
--------------------------------------------------------
* E1: ER = 15.25 (MeV) EG = 4.41 (MeV) SIG = 230.00 (mb)
ER = 6.20 (MeV) EG = 2.20 (MeV) SIG = 3.90 (mb)
ER = 2.10 (MeV) EG = 5.60 (MeV) SIG = 0.40 (mb)
* M1: ER = 7.97 (MeV) EG = 4.00 (MeV) SIG = 1.09 (mb)
* E2: ER = 12.25 (MeV) EG = 4.48 (MeV) SIG = 2.96 (mb)
--------------------------------------------------------
References
1) Anufriev, V.A. et al.: AE, 63, (5), 346 (1987).
2) Katoh, T. et al.: J. Nucl. Sci. Technol., 34,431 (1997).
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) McFadden,L. and Satchler,G.R.: Nucl. Phys. 84, 177 (1966).
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).