24-Cr- 54 JAEA EVAL-Feb21 N.Iwamoto DIST-DEC21 20210228 ----JENDL-5 MATERIAL 2437 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 09-12 The data above the resolved resonance region were evaluated and compiled by N.Iwamoto. 21-02 The resonance parameters were replaced into the data analyzed by the ORNL group. Parial cross sections and energy-angle distributions of charged particle emission were added in MF3,6. 21-11 revised by O.Iwamoto (MF8/MT4) added 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 (R-M formula) : below 834 keV Adopted resonance paramters were evaluated with R-matrix code SAMMY. The evaluation details in Appendix A were taken from ENDF/B-VIII.0. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 2.95564E+00 Elastic 2.54443E+00 n,gamma 4.11198E-01 1.98719E-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 /1/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /1/. MT= 16 (n,2n) cross section Calculated with CCONE code /1/. MT= 17 (n,3n) cross section Calculated with CCONE code /1/. MT= 22 (n,na) cross section Calculated with CCONE code /1/. MT= 28 (n,np) cross section Calculated with CCONE code /1/. MT= 51-91 (n,n') cross section Calculated with CCONE code /1/. MT=102 Capture cross section Calculated with CCONE code /1/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /1/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /1/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /1/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /1/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /1/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with CCONE code /1/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /1/. MT= 16 (n,2n) reaction Calculated with CCONE code /1/. MT= 17 (n,3n) reaction Calculated with CCONE code /1/. MT= 22 (n,na) reaction Calculated with CCONE code /1/. MT= 28 (n,np) reaction Calculated with CCONE code /1/. MT= 51-91 (n,n') reaction Calculated with CCONE code /1/. MT=102 Capture reaction Calculated with CCONE code /1/. MT=600-649 (n,p) reaction Calculated with CCONE code /1/. MT=650-699 (n,d) reaction Calculated with CCONE code /1/. MT=700-749 (n,t) reaction Calculated with CCONE code /1/. MT=750-799 (n,He3) reaction Calculated with CCONE code /1/. MT=800-849 (n,a) reaction Calculated with CCONE code /1/. MF= 8 Information on decay data MT= 5 Total reaction (except fission) 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,2n) 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= 28 (n,np) 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. MF=32 Covariances of Resonance Parameters MT=151 Adopted covariances of resonance paramters were evaluated with R-matrix code SAMMY. The evaluation details in Appendix A were taken from ENDF/B-VIII.0. ***************************************************************** Nuclear Model Calculation with CCONE code /1/ ***************************************************************** Models and parameters used in the CCONE calculation 1) Optical model * optical model potential neutron omp: Kunieda,S. et al./2/ (+) proton omp: Koning,A.J. and Delaroche,J.P./3/ (+) deuteron omp: Lohr,J.M. and Haeberli,W./4/ triton omp: Becchetti Jr.,F.D. and Greenlees,G.W./5/ He3 omp: Becchetti Jr.,F.D. and Greenlees,G.W./5/ alpha omp: McFadden,L. and Satchler,G.R./6/ (+) (+) omp parameters were modified. * DWBA calculation levels: 1,2 (see Table 1) 2) Two-component exciton model/7/ * Global parametrization of Koning-Duijvestijn/8/ was used. * Gamma emission channel/9/ was added to simulate direct and semi-direct capture reaction. 3) Hauser-Feshbach statistical model * Width fluctuation correction/10/ 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/11/. Parameters are shown in Table 2. * Gamma-ray strength function of generalized Lorentzian form /12/,/13/ 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 Cr-54 --------------------------------- No. Ex(MeV) J PI, DWBA: beta --------------------------------- 0 0.00000 0 + 1 0.83486 2 + 0.21 2 1.82393 4 + 0.05 3 2.61968 2 + 4 2.82962 0 + 5 3.07407 2 + 6 3.15957 4 + 7 3.22245 6 + 8 3.39341 2 - 9 3.43688 2 + 10 3.46800 2 - 11 3.51400 0 + 12 3.65523 4 + 13 3.72003 1 + 14 3.78571 4 + 15 3.79854 4 + 16 3.86102 2 + 17 3.87040 1 + 18 3.92555 1 + 19 3.92769 2 + 20 3.98742 1 - 21 4.01290 0 + 22 4.04330 5 + 23 4.08325 2 + 24 4.12600 2 + 25 4.12705 3 - 26 4.19080 2 + 27 4.21751 2 + 28 4.23910 2 + 29 4.25640 2 + 30 4.38095 1 - 31 4.45100 4 + 32 4.45840 1 + 33 4.57080 2 - 34 4.58300 0 + 35 4.61800 2 - 36 4.63360 2 + 37 4.68150 8 + 38 4.68700 3 - 39 4.74000 3 - --------------------------------- Table 2. Level density parameters -------------------------------------------------------- Nuclide a* Pair Eshell T E0 Ematch 1/MeV MeV MeV MeV MeV MeV -------------------------------------------------------- Cr- 55 8.2900 1.6181 0.4243 1.1150 -0.7353 8.3001 Cr- 54 7.6400 3.2660 -0.3078 1.3615 -0.2907 12.8510 Cr- 53 7.8100 1.6483 -1.1345 1.2832 -0.7530 9.9152 Cr- 52 6.6800 3.3282 -1.3204 1.6541 -0.9930 16.2114 V- 54 7.6771 0.0000 0.8258 1.2282 -3.0179 7.6939 V- 53 8.3000 1.6483 0.7140 1.0721 -0.5097 7.7958 V- 52 7.1000 0.0000 -0.6140 1.2996 -2.0622 7.3847 Ti- 53 8.1924 1.6483 0.9098 0.5784 2.0951 2.6483 Ti- 52 7.4405 3.3282 0.9095 1.1982 0.7905 10.2429 Ti- 51 7.6300 1.6803 -0.3127 1.1333 0.1795 7.4616 Ti- 50 7.2500 3.3941 -0.4613 1.2919 1.1007 10.9863 -------------------------------------------------------- Table 3. Gamma-ray strength function for Cr- 55 -------------------------------------------------------- * E1: ER = 17.80 (MeV) EG = 6.50 (MeV) SIG = 88.00 (mb) * M1: ER = 10.78 (MeV) EG = 4.00 (MeV) SIG = 1.34 (mb) * E2: ER = 16.57 (MeV) EG = 5.45 (MeV) SIG = 1.14 (mb) -------------------------------------------------------- ***************************************************************** Appendix A from ENDF/B-VIII.0 ***************************************************************** 24-Cr- 54 ORNL Resonance Evaluation Including Covariance L. C. Leal, H. Derrien, K. Guber, G. Arbanas and D. Wiarda Resolved resonance parameter evaluation for Cr-54 was done with the computer code SAMMY. Transmission measurements for highly enriched samples of chromium isotopes, done by Harvey et al., were used in the evaluations.[1] One transmission measurement for Cr-54 done with a 99.87% enriched sample were used in the evaluation. The transmission measurement was done at the Oak Ridge Electron Linear Accelerator (ORELA) of the Oak Ridge National Laboratory. The transmission data were measured at the 201-meter flight-path in the energy range of 13-850 KeV. Thermal cross section data available in the EXFOR data system were also included in the evaluation. A set of resonance parameter describing the experimental data was obtained. Resonance parameter covariance matrices were also obtained in the SAMMY evaluation process. The Cr-54 evaluation was done in the energy region 10-5 eV 834 keV.[2] Thermal cross section obtained in the present evaluation are compared to the values listed in the Atlas of Neutron Resoances in the following table: Cross Section ORNL Atlas Capt 0.41+/-0.04 0.41+/-0.04 Total 2.96+/-0.11 - Scat 2.55+/-0.10 2.54+/-0.10 ORNL ENDFBVII.0 JENDL4 Res. Int 0.214+/-0.021 0.202 0.204 - [ref 1] J. Harvey, personal communication, Transmission Data for Chromium Isotopes, January 2007. [ref 2] Evaluation of the Chromium Resonance Parameters Including Resonance Parameter Covariance, L. Leal, H. Derrien K. Guber, G. Arbanas, and D. Wiarda, International Conference on Nuclear Data for Science and Technology (ND2010), Jeju Island, Korea, April 26-30, 2010. ***************************************************************** References 1) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007). 2) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007). 3) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003) [Global potential]. 4) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974). 5) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept. J.H.Williams Lab., Univ. Minnesota (1969). 6) McFadden,L. and Satchler,G.R.: Nucl. Phys. 84, 177 (1966). 7) Kalbach,C.: Phys. Rev. C33, 818 (1986). 8) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004). 9) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985). 10) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980). 11) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151 (1994). 12) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990). 13) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).