31-Ga- 69 JAEA EVAL-MAY12 K.Shibata (JAEA) JNST 50, 277 (2013) DIST-DEC21 20180514 ----JENDL-5 MATERIAL 3125 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2012-05 Re-evaluated /1/ by K.Shibata. 2018-05 Activation cross sections added by K.Shibata. 21-11 revised by O.Iwamoto (MF8/MT4) added 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 5.9keV Negative energy level parameters were adjusted to reproduce Koester's data/2/. Evaluation was mainly based on Ohkubo's data/3/ and Mughabghab's compilation/4/. The data are the same as those of JENDL-4.0. *** Negative resonance ************************************* The parameters for the negative resonance were re-adjusted so as to reproduce the thermal capture cross sections measured by Son et al./5/ The recommended thermal cross sectitons /6/ were also considered. ************************************************************ Unresolved resonance region: 5.9 keV - 1 MeV The parameters were obtained by fitting to the evaluated total and capture cross sections. The unresolved resonance parameters should be used only for self-shielding calculation. The parameters were obtained so as to reproduce the total and capture cross sections calculated with POD code /7/. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 9.4005E+00 Elastic 7.6825E+00 n,gamma 1.7180E+00 1.8111E+01 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with POD code /7/. MT= 2 Elastic scattering cross section The elastic scattering cross section was obtained by subtracting the non-elastic cross section from the total cross sections. MT= 3 Non-elastic cross section Sum of partial non-elastic cross sections. MT= 4,51-91 (n,n') cross section Calculated with POD code /7/. MT= 16 (n,2n) cross section Calculated with POD code /7/. MT= 17 (n,3n) cross section Calculated with POD code /7/. MT= 22 (n,na) cross section Calculated with POD code /7/. MT= 28 (n,np) cross section Calculated with POD code /7/. MT= 32 (n,nd) cross section Calculated with POD code /7/. MT=102 Capture cross section Calculated with POD code /7/. MT=103 (n,p) cross section Sum of partial cross sections. MT=104 (n,d) cross section Calculated with POD code /7/. MT=105 (n,t) cross section Calculated with POD code /7/. MT=106 (n,He3) cross section Calculated with POD code /7/. MT=107 (n,a) cross section Calculated with POD code /7/. MT=203 (n,xp) cross section Calculated with POD code /7/. MT=204 (n,xd) cross section Calculated with POD code /7/. MT=205 (n,xt) cross section Calculated with POD code /7/. MT=206 (n,xHe3) cross section Calculated with POD code /7/. MT=207 (n,xa) cross section Calculated with POD code /7/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with POD code /7/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Neutron spectra calculated with POD/7/. MT= 17 (n,3n) reaction Neutron spectra calculated with POD/7/. MT= 22 (n,na) reaction Neutron spectra calculated with POD/7/. MT= 28 (n,np) reaction Neutron spectra calculated with POD/7/. MT= 32 (n,nd) reaction Neutron spectra calculated with POD/7/. MT= 51 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 52 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 53 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 54 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 55 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 56 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 57 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 58 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 59 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 60 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 61 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 62 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 63 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 64 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 65 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 66 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 67 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 68 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 69 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 70 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 71 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 72 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 73 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 74 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 75 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 76 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 77 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 78 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 79 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 80 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 81 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 82 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 83 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 84 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 91 (n,n') reaction Neutron spectra calculated with POD/7/. MT= 203 (n,xp) reaction Proton spectra calculated with POD/7/. MT= 204 (n,xd) reaction Deuteron spectra calculated with POD/7/. MT= 205 (n,xt) reaction Triton spectra calculated with POD/7/. MT= 206 (n,xHe3) reaction He3 spectra calculated with POD/7/. MT= 207 (n,xa) reaction Alpha spectra calculated with POD/7/. MF= 8 Information on decay data MT= 16 (n,2n) reaction MT= 17 (n,3n) reaction MT= 22 (n,na) reaction MT= 28 (n,np) reaction MT= 32 (n,nd) reaction MT=102 (n,g) reaction MT=103 (n,p) reaction MT=104 (n,d) reaction MT=105 (n,t) reaction MT=106 (n,He3) reaction MT=107 (n,a) reaction MF=10 Nuclide production cross sections MT=103 Partial (n,p) reactions Calculated with POD code /7/. Below 13.4 MeV, the ground- state data were modified by considering JEFF-3.1/A data. The meta-stable data remain unchanged from POD calculations. MF=12 Gamma-ray multiplicities MT= 3 Non-elastic gamma emission Calculated with POD code /7/. MF=14 Gamma-ray angular distributions MT= 3 Non-elastic gamma emission Assumed to be isotropic. MF=15 Gamma-ray spectra MT= 3 Non-elastic gamma emission Calculated with POD code /7/. *************************************************************** * Nuclear Model Calculations with POD Code /7/ * *************************************************************** 1. Theoretical models The POD code is based on the spherical optical model, the distorted-wave Born approximaiton (DWBA), one-component exciton preequilibrium model, and the Hauser-Feshbach-Moldauer statis- tical model. With the preequilibrim model, semi-empirical pickup and knockout process can be taken into account for composite-particle emission. The gamma-ray emission from the compound nucleus can be calculated within the framework of the exciton model. The code is capable of reading in particle transmission coefficients calculated by separate spherical or coupled-channel optical model code. 2. Optical model parameters Neutrons: Coupled-channel optical model parameters /8/ Protons: Koning and Delaroche /9/ Deuterons: Lohr and Haeberli /10/ Tritons: Becchetti and Greenlees /11/ He-3: Becchetti and Greenlees /11/ Alphas: Lemos /12/ potentials modified by Arthur and Young /13/ 3. Level scheme of Ga- 69 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 3/2 - 1 0.31869 1/2 - 2 0.57421 5/2 - 3 0.87213 3/2 - 4 1.02858 1/2 - 5* 1.10703 5/2 - 6 1.13400 1/2 - 7* 1.33669 7/2 - 8 1.48814 7/2 - 9 1.52576 3/2 - 10 1.72370 5/2 - 11 1.76477 9/2 - 12 1.89163 3/2 - 13 1.92423 7/2 - 14 1.97239 9/2 + 15 1.97310 1/2 - 16 2.00765 3/2 - 17 2.02384 5/2 - 18 2.04522 5/2 - 19 2.19800 9/2 + 20 2.21927 5/2 - 21 2.25098 3/2 - 22 2.31954 5/2 + 23 2.35329 5/2 + 24 2.42332 3/2 - 25 2.42868 7/2 - 26 2.45883 7/2 - 27 2.48570 5/2 + 28 2.52980 3/2 - 29 2.56440 7/2 + 30 2.57254 9/2 + 31 2.60000 5/2 - 32 2.61400 1/2 - 33 2.66030 3/2 - 34 2.66829 11/2 - ------------------------- Levels above 2.67829 MeV are assumed to be continuous. The symbol (*) stands for the excited level involved in the coupled-channel calculation. 4. Level density parameters Energy-dependent parameters of Mengoni-Nakajima /14/ were used ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- Ga- 70 9.327 0.000 2.337 0.973 -2.875 7.627 1.598 Ga- 69 8.997 1.445 2.185 0.902 -0.433 7.476 2.668 Ga- 68 9.282 0.000 1.568 1.037 -3.150 8.243 1.344 Ga- 67 8.778 1.466 1.090 1.056 -1.152 9.129 2.457 Zn- 69 9.482 1.445 2.644 0.956 -1.539 9.105 1.633 Zn- 68 8.534 2.910 1.955 1.171 -1.144 12.907 3.732 Zn- 67 9.462 1.466 1.848 1.042 -2.076 10.192 1.875 Cu- 67 8.778 1.466 1.483 0.699 1.265 4.284 2.940 Cu- 66 9.511 0.000 0.918 0.842 -1.246 4.898 1.577 Cu- 65 8.558 1.488 0.522 1.103 -1.078 9.278 3.036 ---------------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Generalized Lorentzian (GLO) /15/ 6. Preequilibrium process Preequilibrium is on for n, p, d, t, He-3, and alpha. Preequilibrium capture is on. References 1) K.Shibata, J. Nucl. Sci. Technol., 50, 277 (2013). 2) L.Koester et al., Z. Phys. A318, 347 (1984). 3) M.Ohkubo et al., JAERI-M 90-213 (1990). 4) S.F.Mughabghab et al., "Neutron Cross Section Vol.1 Part A," Academic Press (1981). 5) P.N.Son et al., J. Korean Phys. Soc. Vol.59, No.2, 1761 (2011). 6) S.F.Mughabghab, "Atlas of Neutron Resonances," Elsevier (2006). 7) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 8) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 9) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 10) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 11) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization Phenomena in Nuclear Reactions," p.682, The University of Wisconsin Press (1971). 12) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 13) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 14) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 (1994). 15) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).