39-Y - 90 JAEA EVAL-OCT09 A.Ichihara, K.Shibata, S.Kunieda+ DIST-DEC21 20091201 ----JENDL-5 MATERIAL 3928 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 09-10 Evaluated by A.Ichihara. 21-11 revised by O.Iwamoto (MF8/MT4,16,17,22,28,32,102-107) JENDL/AD-2017 adopted (MF9/MT102) JENDL/AD-2017 adopted (MF10/MT4,16) JENDL/AD-2017 based MF= 1 General information MT=451 Descriptive data and directory Cross sections were calculated with the POD code/1/ in the neutron energy range from 200 eV to 20 MeV. Elastic scattering cross section below 200 eV was estimated with an effective scattering radius 6.74 fm of Y-89/2/. Capture cross section at 0.0253 eV was estimated to be 3.25 b, which is half of a measured upper limit by Smith-Reeder/3/. Capture cross section below 200 eV was obtained assuming the 1/v relation. MF= 2 Resonance parameters MT=151 Unresolved resonance region : 200 eV - 200 keV The unresolved resonance parameters were calculated using the ASREP code/4/. The parameters should be used only for self-shielding calculation. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 9.0231E+00 Elastic 5.7427E+00 n,gamma 3.2513E+00 6.4125E+00 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with POD code /1/. MT= 2 Elastic scattering cross section Calculated as (total - sum of partial cross sections). MT= 3 Non-elastic cross section Calculated as sum of partial cross sections. MT= 4,51-91 (n,n') cross section Calculated with POD code /1/. MT= 16 (n,2n) cross section Calculated with POD code /1/. MT= 17 (n,3n) cross section Calculated with POD code /1/. MT= 22 (n,na) cross section Calculated with POD code /1/. MT= 28 (n,np) cross section Calculated with POD code /1/. MT= 32 (n,nd) cross section Calculated with POD code /1/. MT=102 Capture cross section Calculated with POD code /1/. MT=103 (n,p) cross section Calculated with POD code /1/. MT=104 (n,d) cross section Calculated with POD code /1/. MT=105 (n,t) cross section Calculated with POD code /1/. MT=106 (n,He3) cross section Calculated with POD code /1/. MT=107 (n,a) cross section Calculated with POD code /1/. MT=203 (n,xp) cross section Calculated with POD code /1/. MT=204 (n,xd) cross section Calculated with POD code /1/. MT=205 (n,xt) cross section Calculated with POD code /1/. MT=206 (n,xHe3) cross section Calculated with POD code /1/. MT=207 (n,xa) cross section Calculated with POD code /1/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with POD code /1/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Neutron spectra calculated with POD/1/. MT= 17 (n,3n) reaction Neutron spectra calculated with POD/1/. MT= 22 (n,na) reaction Neutron spectra calculated with POD/1/. MT= 28 (n,np) reaction Neutron spectra calculated with POD/1/. MT= 32 (n,nd) reaction Neutron spectra calculated with POD/1/. MT= 51 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 52 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 53 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 54 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 55 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 56 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 57 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 58 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 59 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 60 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 61 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 62 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 63 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 64 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 65 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 66 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 67 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 68 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 69 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 70 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 71 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 72 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 73 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 74 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 75 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 76 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 77 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 78 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 79 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 80 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 81 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 82 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 83 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 91 (n,n') reaction Neutron spectra calculated with POD/1/. MT= 203 (n,xp) reaction Proton spectra calculated with POD/1/. MT= 204 (n,xd) reaction Deuteron spectra calculated with POD/1/. MT= 205 (n,xt) reaction Triton spectra calculated with POD/1/. MT= 206 (n,xHe3) reaction He3 spectra calculated with POD/1/. MT= 207 (n,xa) reaction Alpha spectra calculated with POD/1/. MF=12 Gamma-ray multiplicities MT= 3 Non-elastic gamma emission Calculated with POD code /1/. 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 /1/. *************************************************************** * Nuclear Model Calculations with POD Code /1/ * *************************************************************** 1. Theoretical models The POD code is based on the spherical optical model, the distorted-wave Born approximation (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: Koning and Delaroche /5/ Protons: Koning and Delaroche /5/ The radius parameter r_V = 1.25 fm was used in the calculation. Deuterons: Lohr and Haeberli /6/ Tritons: Becchetti and Greenlees /7/ He-3: Becchetti and Greenlees /7/ Alphas: Lemos /8/ potentials modified by Arthur and Young /9/. The radius parameters r_V = r_I = 1.40 fm were used in the calculation. 3. Level scheme of Y - 90 Nuclear discrete levels were obtained from RIPL-2/10/. ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 2 - 1 0.20253 3 - 2 0.68167 7 + 3 0.77677 2 + 4 0.95367 3 + 5 1.04751 6 + 6 1.18991 7 - 7 1.21169 1 - 8 1.29820 5 + 9 1.37125 1 - 10 1.41666 0 + 11 1.57177 1 - 12 1.64111 3 - 13 1.76110 3 - 14 1.81170 3 - 15 1.81519 1 + 16 1.96090 4 + 17 2.00317 7 - 18 2.03000 4 + 19 2.08910 6 + 20 2.18496 3 + 21 2.21668 8 + 22 2.24090 4 + 23 2.24461 2 + 24 2.31300 1 + 25 2.32426 3 + 26 2.36613 1 - 27 2.45519 4 + 28 2.47420 2 - 29 2.50473 0 + 30 2.51700 6 + 31 2.56581 2 - 32 2.58969 2 + 33 2.62380 2 - ------------------------- Levels above 2.63380 MeV are assumed to be continuous. 4. Level density parameters Energy-dependent parameters of Mengoni-Nakajima /11/ were used --------------------------------------------------- Nuclei a* Pair T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV --------------------------------------------------- Y - 91 11.338 1.258 0.772 0.115 5.977 2.689 Y - 90 10.454 0.000 0.865 -0.779 4.677 2.624 Y - 89 11.127 1.272 0.682 1.455 3.665 4.023 Y - 88 11.494 0.000 0.820 -1.352 5.191 1.596 Sr- 90 11.748 2.530 0.778 1.141 7.584 3.627 Sr- 89 10.953 1.272 0.720 1.044 4.474 4.050 Sr- 88 11.473 2.558 0.785 1.929 6.625 5.199 Rb- 88 10.411 0.000 0.994 -2.333 7.292 1.964 Rb- 87 10.916 1.286 0.895 -0.274 7.103 3.099 Rb- 86 9.930 0.000 0.984 -2.108 6.936 2.025 --------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Standard Lorentzian (SLO) /12/ The position and width parameters in the E1 radiation were taken from the tabulation of Dietrich and Berman/13/. 6. Preequilibrium process Preequilibrium is on for n, p, d, t, He-3, and alpha. The single particle state density parameters were 6.958, 6.923, 7.202, 6.359, 5.500, 6.383, 6.188 (MeV^-1) for Y-91, Y-90, Sr-90, Rb-87, Sr-89, Sr-88, and Rb-88. Effects of the particle pickup (and knockout for alpha) were estimated using the semi-empirical formulas by Kalbach/14/. These components were multiplied by a factor of two and added to the statistical model calculation. Preequilibrium capture is on (the parameters were obtained from /13/). References 1) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 2) S.F.Mughabghab, "Atlas of Neutron Resonances," Elsevier (2006). 3) R.R.Smith, S.D.Reeder, J. Chem. Phys. 23, 2108 (1955). 4) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999) [in Japanese]. 5) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 6) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 7) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization Phenomena in Nuclear Reactions," p.682, The University of Wisconsin Press (1971). 8) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 9) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 10) T.Belgya et al., IAEA-TECDOC-1506 (2006). 11) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 (1994). 12) M.Brink, Ph.D thesis, Oxford University, 1955. 13) S.S.Dietrich, B.L.Berman, Atom. Data Nucl. Data Tables, 38, 199 (1988). 14) C.Kalbach, Z. Phys. A283, 401 (1977).