55-Cs-133 JAEA+ EVAL-Apr09 N.Iwamoto,H.Matsunobu DIST-DEC21 20100119 ----JENDL-5 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. 21-09 MF3,6/MT600-849 and MF8,9,10 were added and the resonance paramters were updated by N.Iwamoto. 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.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. In JENDL-5. the resonance parameters were replaced into the data of Block et al./15/. Unresolved resonance region : 5.98 keV - 100 keV The unresolved resonance paramters (URP) were determined by ASREP code /16/ so as to reproduce the evaluated total and capture cross sections calculated with optical model code OPTMAN /17/ and CCONE /18/. 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 3.54526E+01 Elastic 3.25985E+00 n,gamma 3.21927E+01 4.58408E+02 n,alpha 1.10690E-10 8.56249E-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= 4,51-91 (n,n') cross section Calculated with CCONE code /18/. MT= 16 (n,2n) cross section Calculated with CCONE code /18/. MT= 17 (n,3n) cross section Calculated with CCONE code /18/. MT= 22 (n,na) cross section Calculated with CCONE code /18/. MT= 24 (n,2na) cross section Calculated with CCONE code /18/. MT= 28 (n,np) cross section Calculated with CCONE code /18/. MT= 29 (n,n2a) cross section Calculated with CCONE code /18/. MT= 32 (n,nd) cross section Calculated with CCONE code /18/. MT= 33 (n,nt) cross section Calculated with CCONE code /18/. MT= 34 (n,nHe3) cross section Calculated with CCONE code /18/. MT= 41 (n,2np) cross section Calculated with CCONE code /18/. MT= 44 (n,n2p) cross section Calculated with CCONE code /18/. MT= 45 (n,npa) cross section Calculated with CCONE code /18/. MT= 51-91 (n,n') cross section Calculated with CCONE code /18/. MT=102 Capture cross section Calculated with CCONE code /18/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /18/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /18/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /18/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /18/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /18/. MT=108 (n,2a) cross section Calculated with CCONE code /18/. MT=111 (n,2p) cross section Calculated with CCONE code /18/. MT=112 (n,pa) cross section Calculated with CCONE code /18/. MT=115 (n,pd) cross section Calculated with CCONE code /18/. MT=116 (n,pt) cross section Calculated with CCONE code /18/. MT=117 (n,da) cross section Calculated with CCONE code /18/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with CCONE code /18/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /18/. MT= 17 (n,3n) reaction Calculated with CCONE code /18/. MT= 22 (n,na) reaction Calculated with CCONE code /18/. MT= 24 (n,2na) reaction Calculated with CCONE code /18/. MT= 28 (n,np) reaction Calculated with CCONE code /18/. MT= 29 (n,n2a) reaction Calculated with CCONE code /18/. MT= 32 (n,nd) reaction Calculated with CCONE code /18/. MT= 33 (n,nt) reaction Calculated with CCONE code /18/. MT= 34 (n,nHe3) reaction Calculated with CCONE code /18/. MT= 41 (n,2np) reaction Calculated with CCONE code /18/. MT= 44 (n,n2p) reaction Calculated with CCONE code /18/. MT= 45 (n,npa) reaction Calculated with CCONE code /18/. MT= 51-91 (n,n') reaction Calculated with CCONE code /18/. MT=102 Capture reaction Calculated with CCONE code /18/. MT=600-649 (n,p) reaction Calculated with CCONE code /18/. MT=650-699 (n,d) reaction Calculated with CCONE code /18/. MT=700-749 (n,t) reaction Calculated with CCONE code /18/. MT=750-799 (n,He3) reaction Calculated with CCONE code /18/. MT=800-849 (n,a) reaction Calculated with CCONE code /18/. MF= 8 Information on decay data MT= 4 (n,n') reaction Decay chain is given in the decay data file. MT= 16 (n,2n) reaction Decay chain is given in the decay data file. MT= 17 (n,3n) reaction Decay chain is given in the decay data file. MT= 22 (n,na) reaction Decay chain is given in the decay data file. MT= 24 (n,2na) reaction Decay chain is given in the decay data file. MT= 28 (n,np) reaction Decay chain is given in the decay data file. MT= 29 (n,n2a) reaction Decay chain is given in the decay data file. MT= 32 (n,nd) reaction Decay chain is given in the decay data file. MT= 33 (n,nt) reaction Decay chain is given in the decay data file. MT= 34 (n,nHe3) reaction Decay chain is given in the decay data file. MT= 41 (n,2np) reaction Decay chain is given in the decay data file. MT= 44 (n,n2p) reaction Decay chain is given in the decay data file. MT= 45 (n,npa) reaction Decay chain is given in the decay data file. MT=102 Capture reaction Decay chain is given in the decay data file. MT=103 (n,p) reaction Decay chain is given in the decay data file. MT=104 (n,d) reaction Decay chain is given in the decay data file. MT=105 (n,t) reaction Decay chain is given in the decay data file. MT=106 (n,He3) reaction Decay chain is given in the decay data file. MT=107 (n,a) reaction Decay chain is given in the decay data file. MT=108 (n,2a) reaction Decay chain is given in the decay data file. MT=111 (n,2p) reaction Decay chain is given in the decay data file. MT=112 (n,pa) reaction Decay chain is given in the decay data file. MT=115 (n,pd) reaction Decay chain is given in the decay data file. MT=116 (n,pt) reaction Decay chain is given in the decay data file. MT=117 (n,da) reaction Decay chain is given in the decay data file. MF= 9 Isomeric branching ratios MT=102 Capture reaction Calculated with CCONE code /18/. MT=103 (n,p) reaction Calculated with CCONE code /18/. MT=107 (n,a) reaction Calculated with CCONE code /18/. MF=10 Nuclide production cross sections MT= 32 (n,nd) reaction Calculated with CCONE code /18/. MT= 41 (n,2np) reaction Calculated with CCONE code /18/. MT=105 (n,t) reaction Calculated with CCONE code /18/. ***************************************************************** Nuclear Model Calculation with CCONE code /18/ ***************************************************************** Models and parameters used in the CCONE calculation 1) Optical model * optical model potential neutron omp: Kunieda,S. et al./19/ (+) proton omp: Koning,A.J. and Delaroche,J.P./20/ deuteron omp: Lohr,J.M. and Haeberli,W./21/ triton omp: Becchetti Jr.,F.D. and Greenlees,G.W./22/ He3 omp: Becchetti Jr.,F.D. and Greenlees,G.W./22/ alpha omp: McFadden,L. and Satchler,G.R./23/ (+) omp parameters were modified. 2) Two-component exciton model/24/ * Global parametrization of Koning-Duijvestijn/25/ was used. * Gamma emission channel/26/ was added to simulate direct and semi-direct capture reaction. 3) Hauser-Feshbach statistical model * Width fluctuation correction/27/ 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/28/. Parameters are shown in Table 2. * Gamma-ray strength function of generalized Lorentzian form /29/,/30/ 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 1) Landon, H.H. and Sailor, V.L. : PR, 93, 1030 (1954). 2) Harvey, J.A., et al.: Phys. Rev., 99, 10 (1955). 3) Garg, J.B. et al. : Phys. Rev., B137, 547 (1965). 4) Jung, H.H., et al.: "Proc. 2nd IAEA Conf. on Nucl. Data for 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). 8) Anufriev, V.A., et al.: AE, 43, 201 (1977). 9) Macklin, R.L. : Nucl. 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