33-As- 75 JAEA EVAL-APR09 K.Shibata, G.Chiba, A.Ichihara+ DIST-MAY10 20100107 ----JENDL-4.0 MATERIAL 3325 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 09-04 Evaluated by K.Shibata, G.Chiba, A.Ichihara, and S.Kunieda. 10-01 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 region (MLBW formula) : Below 9.7 keV Resonance parameters for the 39 levels from 47.0 to 2616 eV were evaluated on the basis of the data given by Mughabghab et al./1/ Resonance energies for the 210 levels from 2676 to 11960 eV were based on the measurement by Macklin/2/. Neutron and radiation widths for the 210 levels were determined by different methods according to the following three conditions, respectively. 1) In cases where total width and neutron capture area measured by macklin are given for a resonance level, the neutron and radiation widths were simultaneously obtained by solving a quadratic equation. 2) In cases where neutron capture area measured by Macklin and 2g*(neutron width) given by Mughabghab et al. are available for a resonance level, the radiation widths were derived from the both data. 3) In cases where only neutron capture area by Macklin is available, or g*(neutron width) by Mughabghab et al. is smaller than neutron capture area by Macklin for a resonance level, the average radiation width of 318 meV given by Macklin was adopted for the level. The neutron width was derived from this average radiation width and the neutron capture area. Neutron orbital angular momentum l of some resonances was estimated with a method of Bollinger and Thomas/3/. Total spin j of some resonances was tentatively estimated with a random number method. Scattering radius was taken from Mughabghab et al. Two negative resonances were added so as to reproduce the thermal capture and scattering cross sections given by Mughabghab et al. In JENDL-4, the energy of a negative resonace was changed to 100 meV so as to reproduce the thermal capture cross section measured by Mustafa Karadag et al./4/ Unresolved resonance region: 9.7 keV - 500 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 9.6199E+00 Elastic 5.4673E+00 n,gamma 4.1525E+00 6.3735E+01 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with POD code /5/. 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 /5/. MT= 16 (n,2n) cross section Calculated with POD code /5/. MT= 17 (n,3n) cross section Calculated with POD code /5/. MT= 22 (n,na) cross section Calculated with POD code /5/. MT= 28 (n,np) cross section Calculated with POD code /5/. MT= 32 (n,nd) cross section Calculated with POD code /5/. MT=102 Capture cross section Calculated with POD code /5/. MT=103 (n,p) cross section Calculated with POD code /5/. MT=104 (n,d) cross section Calculated with POD code /5/. MT=105 (n,t) cross section Calculated with POD code /5/. MT=106 (n,He3) cross section Calculated with POD code /5/. MT=107 (n,a) cross section Calculated with POD code /5/. MT=203 (n,xp) cross section Calculated with POD code /5/. MT=204 (n,xd) cross section Calculated with POD code /5/. MT=205 (n,xt) cross section Calculated with POD code /5/. MT=206 (n,xHe3) cross section Calculated with POD code /5/. MT=207 (n,xa) cross section Calculated with POD code /5/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with POD code /5/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Neutron spectra calculated with POD/5/. MT= 17 (n,3n) reaction Neutron spectra calculated with POD/5/. MT= 22 (n,na) reaction Neutron spectra calculated with POD/5/. MT= 28 (n,np) reaction Neutron spectra calculated with POD/5/. MT= 32 (n,nd) reaction Neutron spectra calculated with POD/5/. MT= 51 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 52 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 53 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 54 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 55 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 56 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 57 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 58 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 59 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 60 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 61 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 62 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 63 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 64 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 65 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 66 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 67 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 68 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 69 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 70 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 71 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 72 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 73 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 74 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 75 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 76 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 77 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 78 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 79 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 80 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 91 (n,n') reaction Neutron spectra calculated with POD/5/. A giant resonance was considered at an excitation energy of 2.8 MeV and it was broadened with a Gaussina distribution with FWHM=1.41 MeV. MT= 203 (n,xp) reaction Proton spectra calculated with POD/5/. MT= 204 (n,xd) reaction Deuteron spectra calculated with POD/5/. MT= 205 (n,xt) reaction Triton spectra calculated with POD/5/. MT= 206 (n,xHe3) reaction He3 spectra calculated with POD/5/. MT= 207 (n,xa) reaction Alpha spectra calculated with POD/5/. MF=12 Gamma-ray multiplicities MT= 3 Non-elastic gamma emission Calculated with POD code /5/. 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 /5/.*************************************************************** * Nuclear Model Calculations with POD Code /5/ * *************************************************************** 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 /6/ Protons: Koning and Delaroche /7/ Deuterons: Lohr and Haeberli /8/ Tritons: Becchetti and Greenlees /9/ He-3: Becchetti and Greenlees /9/ Alphas: Lemos /10/ potentials modified by Arthur and Young /11/ 3. Level scheme of As- 75 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 3/2 - 1 0.19861 1/2 - 2 0.26466 3/2 - 3 0.27954 5/2 - 4 0.30392 9/2 + 5 0.40066 5/2 + 6 0.46860 1/2 - 7 0.57222 5/2 - 8 0.58500 3/2 - 9 0.61770 3/2 - 10 0.82156 7/2 - 11 0.85990 1/2 + 12 0.86480 1/2 - 13 0.88600 3/2 + 14 1.04180 7/2 - 15 1.06430 3/2 - 16 1.07560 3/2 - 17 1.08040 5/2 + 18 1.09550 7/2 - 19 1.10100 1/2 - 20 1.12770 1/2 + 21 1.12800 1/2 - 22 1.17160 11/2 + 23 1.20450 3/2 - 24 1.26310 1/2 + 25 1.30120 5/2 + 26 1.30900 5/2 - 27 1.34930 3/2 - 28 1.37000 3/2 - 29 1.41980 5/2 - 30 1.43030 3/2 + ------------------------- Levels above 1.44030 MeV are assumed to be continuous. 4. Level density parameters Energy-dependent parameters of Mengoni-Nakajima /12/ were used ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- As- 76 9.954 0.000 3.702 0.933 -3.511 8.279 0.669 As- 75 9.648 1.386 3.768 0.921 -1.771 9.165 1.430 As- 74 9.955 0.000 3.777 0.902 -3.209 7.736 0.776 As- 73 9.432 1.404 3.632 1.014 -2.603 10.639 1.344 Ge- 75 9.958 1.386 3.393 0.852 -1.123 8.044 1.603 Ge- 74 9.691 2.790 3.220 0.910 -0.065 10.140 2.711 Ge- 73 10.618 1.404 3.764 0.886 -2.153 9.468 0.994 Ga- 73 9.432 1.404 3.322 0.797 -0.248 6.711 1.528 Ga- 72 9.658 0.000 3.408 0.897 -2.795 7.185 0.684 Ga- 71 9.215 1.424 3.011 0.843 -0.395 7.131 2.396 ---------------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Generalized Lorentzian (GLO) /13/ 6. Preequilibrium process Preequilibrium is on for n, p, d, t, He-3, and alpha. Preequilibrium capture is on. References 1) S.F.Mughabghab et al., Neutron Cross Sections, Vol.1, Part A, (1981). 2) R.L.Macklin, Nucl. Sci. Eng. 99, 133 (1988). 3) L.M.Bollinger, G.E.Thomas, Phys. Rev., 171,1293(1968). 4) Mustafa Karadag et al., Nucl. Phys., A501, 524 (2003). 5) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 6) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 7) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 8) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 9) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization Phenomena in Nuclear Reactions," p.682, The University of Wisconsin Press (1971). 10) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 11) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 12) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 (1994). 13) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).