72-Hf-178 JAEA EVAL-AUG09 K. Shibata (JAEA) DIST-MAY10 20091111 ----JENDL-4.0 MATERIAL 7237 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 09-08 Evaluated by K. Shibata. 09-10 Compiled by K. Shibata. MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resonance parameters Resolved resonance parameters (MLBW formula) : Below 1.5keV JENDL-3.3 was based on the compilation of Mughabghab./1/ In JENDL-4, the data remain unchanged from JENDL-3.3. Unresolved resonance region: 1.5 keV - 220 keV The parameters were obtained by fitting to the total and capture cross sections calculated from POD /2/. 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. (*) (barns) (barns) ---------------------------------------------------------- Total 8.8527E+01 Elastic 4.4735E+00 n,gamma 8.4054E+01 1.9150E+03 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with POD code /2/. MT= 2 Elastic scattering cross section Obtained by subtracting non-elastic cross sections from 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 /2/. MT= 16 (n,2n) cross section Calculated with POD code /2/. MT= 17 (n,3n) cross section Calculated with POD code /2/. MT= 22 (n,na) cross section Calculated with POD code /2/. MT= 28 (n,np) cross section Calculated with POD code /2/. MT= 32 (n,nd) cross section Calculated with POD code /2/. MT=102 Capture cross section Calculated with POD code /2/. MT=103 (n,p) cross section Calculated with POD code /2/. MT=104 (n,d) cross section Calculated with POD code /2/. MT=105 (n,t) cross section Calculated with POD code /2/. MT=106 (n,He3) cross section Calculated with POD code /2/. MT=107 (n,a) cross section Calculated with POD code /2/. MT=203 (n,xp) cross section Calculated with POD code /2/. MT=204 (n,xd) cross section Calculated with POD code /2/. MT=205 (n,xt) cross section Calculated with POD code /2/. MT=206 (n,xHe3) cross section Calculated with POD code /2/. MT=207 (n,xa) cross section Calculated with POD code /2/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with POD code /2/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Neutron spectra calculated with POD/2/. MT= 17 (n,3n) reaction Neutron spectra calculated with POD/2/. MT= 22 (n,na) reaction Neutron spectra calculated with POD/2/. MT= 28 (n,np) reaction Neutron spectra calculated with POD/2/. MT= 32 (n,nd) reaction Neutron spectra calculated with POD/2/. MT= 51 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 52 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 53 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 54 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 55 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 56 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 57 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 58 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 59 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 60 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 61 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 62 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 63 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 64 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 65 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 66 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 67 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 68 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 69 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 70 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 71 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 72 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 73 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 74 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 75 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 76 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 77 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 78 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 79 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 80 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 81 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 82 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 83 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 84 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 85 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 86 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 87 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 88 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 89 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 90 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 91 (n,n') reaction Neutron spectra calculated with POD/2/. MT= 203 (n,xp) reaction Proton spectra calculated with POD/2/. MT= 204 (n,xd) reaction Deuteron spectra calculated with POD/2/. MT= 205 (n,xt) reaction Triton spectra calculated with POD/2/. MT= 206 (n,xHe3) reaction He3 spectra calculated with POD/2/. MT= 207 (n,xa) reaction Alpha spectra calculated with POD/2/. MF=12 Gamma-ray multiplicities MT= 3 Non-elastic gamma emission Calculated with POD code /2/. 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 /2/.*************************************************************** * Nuclear Model Calculations with POD Code /2/ * *************************************************************** 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 /3/ Protons: Koning and Delaroche /4/ Deuterons: Lohr and Haeberli /5/ Tritons: Becchetti and Greenlees /6/ He-3: Becchetti and Greenlees /6/ Alphas: Lemos /7/ potentials modified by Arthur and Young /8/ 3. Level scheme of Hf-178 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 0 + 1 0.09318 2 + 2 0.30662 4 + 3 0.63218 6 + 4 1.05856 8 + 5 1.14742 8 - 6 1.17463 2 + 7 1.19939 0 + 8 1.26025 2 - 9 1.26854 3 + 10 1.27669 2 + 11 1.31007 1 - 12 1.32246 3 - 13 1.36255 2 - 14 1.36409 9 - 15 1.38446 4 + 16 1.40944 4 - 17 1.43362 3 - 18 1.43421 0 + 19 1.44394 0 + 20 1.45036 4 + 21 1.47904 8 - 22 1.49642 2 + 23 1.51259 5 - 24 1.51361 2 + 25 1.51383 4 + 26 1.53315 5 + 27 1.53879 4 - 28 1.55400 6 + 29 1.56153 2 + 30 1.56667 2 - 31 1.57100 10 + 32 1.60147 10 - 33 1.63560 4 + 34 1.63673 5 - 35 1.63976 3 - 36 1.64045 5 + 37 1.64884 6 - 38 1.65146 5 - 39 1.65410 4 + 40 1.69108 6 + ------------------------- Levels above 1.70108 MeV are assumed to be continuous. 4. Level density parameters Energy-dependent parameters of Mengoni-Nakajima /9/ were used. ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- Hf-179 20.645 0.897 1.612 0.514 -0.871 5.514 0.896 Hf-178 20.930 1.799 1.834 0.544 -0.516 7.225 1.691 Hf-177 20.775 0.902 1.759 0.533 -1.190 6.000 0.624 Hf-176 20.775 1.809 1.927 0.538 -0.407 7.077 1.767 Lu-178 20.825 0.000 1.338 0.403 -0.584 2.568 0.300 Lu-177 20.295 0.902 1.742 0.499 -0.639 5.159 1.184 Lu-176 19.534 0.000 1.378 0.516 -1.470 4.263 0.659 Yb-176 20.775 1.809 1.620 0.490 0.295 5.983 1.767 Yb-175 20.006 0.907 1.310 0.518 -0.680 5.317 1.035 Yb-174 20.077 1.819 1.456 0.506 0.310 6.070 2.037 ---------------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Generalized Lorentzian (GLO) /10/ 6. Preequilibrium process Preequilibrium is on for n, p, d, t, He-3, and alpha. Preequilibrium capture is on. References 1) S.F.Mughabghab, Neutron Cross Sections, Vol.2, Part B, (1984). 2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 3) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 4) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 5) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 6) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization Phenomena in Nuclear Reactions," p.682, The University of Wisconsin Press (1971). 7) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 8) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 9) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 (1994). 10) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).