55-Cs-133
55-Cs-133 JAEA+ EVAL-Apr09 N.Iwamoto,H.Matsunobu
DIST-MAY10 20100119
----JENDL-4.0 MATERIAL 5525
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
History
09-04 The resolved resonance parameters were evaluated by
H.Matsunobu,N.Iwamoto.
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 5.98 keV
Evaluation of the resonance parameters for JENDL-3.3 was
performed on the basis of the following experimental data :
Landon and Sailor/1/, Harvey et al./2/, Garg et al.
/3/, Jung et al./4/, Thomas et al./5/, Riehs and
Thomas/6/, Hockenbury et al./7/, Anufriev et al./8/,
Macklin/9/, Popov and Tshetsyak/10/, and Nakajima et al.
/11/.
The neutron orbital angular momentum l were assumed to be 0
for all the resonance levels. For resonance levels whose the
value of total spin j was unknown, the j-values were
estimated tentatively with a random number method. The
radiation widths were derived from the neutron capture areas
measured by Macklin and by Nakajima et al. with given or
estimated j-values. For resonance levels which the radiation
width was unknown, the average radiation width calculated
from the known radiation widths, was adopted. Two negative
resonance levels were added so as to reproduce the thermal
capture cross section of 29.0+-1.5 barns given by Mughabghab
et al./12/
In JENDL-4, resonance energy range from -40 eV to 6 keV was
divided into three regions as follows:
I. low energy region : from -40 eV to 800 eV
II. medium energy region : from 800 eV to 2660 eV
III. high energy region : from 2660 eV to 6000 eV
In low energy region, there are 9 data except Macklin data,
as mentioned above. Furthermore, a new data measured by
Sharapov et al./13/ were available. The data contain s-wave
data of 22 points, p-wave data of 26 points, and d-wave data
of 1 point. In this region, the parameters of 48 levels were
evaluated on the basis of the data by Nakajima et al., by
Garg et al., by Anufriev et al., and by Sharapov et al.
In medium energy region, there are only 2 data by Nakajima
et al. and by Garg et al. In this region, the parameters of
95 levels were evaluated mainly by the data of Nakajima et
al. In high energy region, there are 3 data by Nakajima et
al., by Macklin, and by Garg et al. In this region, the
parameters of 185 levels were evaluated mainly by the data
of Nakajima et al. and of Macklin. The data of Garg et al.
were adopted to amend some missing levels. All of the p-wave
and d-wave data by Sharapov et al. were compiled in JENDL-4.
For the resonance levels whose radiation width was unknown,
the average radiation widths were adopted in the three
regions, respectively. The resorance parameters of two
negative levels were modified so as to reproduce the
thermal capture cross section of 29+-1 barns measured at
0.0253 ev by nakamura et al./14/.
The all s-wave resonance data by Sharapov et al./13/ were
adopted, in order to improve the result of an integral test.
Unresolved resonance region : 5.98 keV - 100 keV
The unresolved resonance paramters (URP) were determined by
ASREP code /15/ so as to reproduce the evaluated total and
capture cross sections calculated with optical model code
OPTMAN /16/ and CCONE /17/. 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 3.2887e+01
Elastic 3.9851e+00
n,gamma 2.8902e+01 4.4624e+02
n,alpha 1.1070e-10
----------------------------------------------------------
(*) 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 /17/.
MT= 16 (n,2n) cross section
Calculated with CCONE code /17/.
MT= 17 (n,3n) cross section
Calculated with CCONE code /17/.
MT= 22 (n,na) cross section
Calculated with CCONE code /17/.
MT= 24 (n,2na) cross section
Calculated with CCONE code /17/.
MT= 28 (n,np) cross section
Calculated with CCONE code /17/.
MT= 29 (n,n2a) cross section
Calculated with CCONE code /17/.
MT= 30 (n,2n2a) cross section
Calculated with CCONE code /17/.
MT= 32 (n,nd) cross section
Calculated with CCONE code /17/.
MT= 33 (n,nt) cross section
Calculated with CCONE code /17/.
MT= 34 (n,nHe3) cross section
Calculated with CCONE code /17/.
MT= 41 (n,2np) cross section
Calculated with CCONE code /17/.
MT= 44 (n,n2p) cross section
Calculated with CCONE code /17/.
MT= 45 (n,npa) cross section
Calculated with CCONE code /17/.
MT= 51-91 (n,n') cross section
Calculated with CCONE code /17/.
MT=102 Capture cross section
Calculated with CCONE code /17/.
MT=103 (n,p) cross section
Calculated with CCONE code /17/.
MT=104 (n,d) cross section
Calculated with CCONE code /17/.
MT=105 (n,t) cross section
Calculated with CCONE code /17/.
MT=106 (n,He3) cross section
Calculated with CCONE code /17/.
MT=107 (n,a) cross section
Calculated with CCONE code /17/.
MT=108 (n,2a) cross section
Calculated with CCONE code /17/.
MT=111 (n,2p) cross section
Calculated with CCONE code /17/.
MT=112 (n,pa) cross section
Calculated with CCONE code /17/.
MT=115 (n,pd) cross section
Calculated with CCONE code /17/.
MT=116 (n,pt) cross section
Calculated with CCONE code /17/.
MT=117 (n,da) cross section
Calculated with CCONE code /17/.
MF= 4 Angular distributions of emitted neutrons
MT= 2 Elastic scattering
Calculated with CCONE code /17/.
MF= 6 Energy-angle distributions of emitted particles
MT= 16 (n,2n) reaction
Calculated with CCONE code /17/.
MT= 17 (n,3n) reaction
Calculated with CCONE code /17/.
MT= 22 (n,na) reaction
Calculated with CCONE code /17/.
MT= 24 (n,2na) reaction
Calculated with CCONE code /17/.
MT= 28 (n,np) reaction
Calculated with CCONE code /17/.
MT= 29 (n,n2a) reaction
Calculated with CCONE code /17/.
MT= 30 (n,2n2a) reaction
Calculated with CCONE code /17/.
MT= 32 (n,nd) reaction
Calculated with CCONE code /17/.
MT= 33 (n,nt) reaction
Calculated with CCONE code /17/.
MT= 34 (n,nHe3) reaction
Calculated with CCONE code /17/.
MT= 41 (n,2np) reaction
Calculated with CCONE code /17/.
MT= 44 (n,n2p) reaction
Calculated with CCONE code /17/.
MT= 45 (n,npa) reaction
Calculated with CCONE code /17/.
MT= 51-91 (n,n') reaction
Calculated with CCONE code /17/.
MT=102 Capture reaction
Calculated with CCONE code /17/.
*****************************************************************
Nuclear Model Calculation with CCONE code /17/
*****************************************************************
Models and parameters used in the CCONE calculation
1) Optical model
* optical model potential
neutron omp: Kunieda,S. et al./18/ (+)
proton omp: Koning,A.J. and Delaroche,J.P./19/
deuteron omp: Lohr,J.M. and Haeberli,W./20/
triton omp: Becchetti Jr.,F.D. and Greenlees,G.W./21/
He3 omp: Becchetti Jr.,F.D. and Greenlees,G.W./21/
alpha omp: McFadden,L. and Satchler,G.R./22/
(+) omp parameters were modified.
2) Two-component exciton model/23/
* Global parametrization of Koning-Duijvestijn/24/
was used.
* Gamma emission channel/25/ was added to simulate direct
and semi-direct capture reaction.
3) Hauser-Feshbach statistical model
* Width fluctuation correction/26/ 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/27/.
Parameters are shown in Table 2.
* Gamma-ray strength function of generalized Lorentzian form
/28/,/29/ 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-133
-------------------
No. Ex(MeV) J PI
-------------------
0 0.00000 7/2 +
1 0.08100 5/2 +
2 0.16061 5/2 +
3 0.38385 3/2 +
4 0.43701 1/2 +
5 0.63256 11/2 +
6 0.64039 3/2 +
7 0.70554 9/2 +
8 0.72830 7/2 -
9 0.76771 9/2 +
10 0.78878 7/2 +
11 0.81906 7/2 +
12 0.87182 7/2 +
13 0.91609 9/2 -
14 0.94160 7/2 +
-------------------
Table 2. Level density parameters
--------------------------------------------------------
Nuclide a* Pair Eshell T E0 Ematch
1/MeV MeV MeV MeV MeV MeV
--------------------------------------------------------
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
Cs-132 15.0210 0.0000 0.5030 0.7096 -2.0934 5.3772
Cs-131 16.2311 1.0484 1.0372 0.6798 -1.3713 6.6283
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
Xe-131 18.6500 1.0484 -0.1767 0.6072 -0.8373 5.8792
Xe-130 16.4000 2.1049 0.1531 0.6510 0.2933 6.9512
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
I-128 16.4000 0.0000 0.6379 0.7507 -3.3087 6.9967
I-127 15.0536 1.0648 1.0709 0.6873 -1.0070 6.2257
--------------------------------------------------------
Table 3. Gamma-ray strength function for Cs-134
--------------------------------------------------------
* 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 = 8.01 (MeV) EG = 4.00 (MeV) SIG = 1.13 (mb)
* E2: ER = 12.31 (MeV) EG = 4.50 (MeV) SIG = 2.99 (mb)
--------------------------------------------------------
References
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2) Harvey, J.A., et al.: Phys. Rev., 99, 10 (1955).
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Reactors, Helsinki 1970", Vol.1, 679.
5) Thomas, B.W., et al.: AERE-PR/NP-18, 23 (1972).
6) Riehs, P. and Thomas, B.W. : "Proc. 2nd Int. Sympos. on
Neutron Capture Gamma-ray Spectroscopy and Related Topics,
Petten 1974", 300.
7) Hockenbury, R.W. et al.: ERDA-NDC-9, 242 (1977).
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[in Japanese].
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[Global potential].
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J.H.Williams Lab., Univ. Minnesota (1969).
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(1994).
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