14-Si- 30 JAEA EVAL-AUG07 K.Shibata, S.Kunieda DIST-MAY10 20091202 ----JENDL-4.0 MATERIAL 1431 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 07-08 Evaluated by K.Shibata and S.Kunieda. 09-12 Compiled by K.Shibata. MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved resonance parameters Resolved resonance region (Reich-Moore formula) : Below 1.50 MeV The resolved resonance parameters were taken from the ENDF/B-VII.0 data, which were evaluated by Leal et al./1/ The following comments were also taken from ENDF/B-VII.0: ------------------------------------------------------------ The following data were included in the analysis: (1) Total cross section data of Perey et al. /2/ for natural silicon, measured on the 47-m flight path at the Oak Ridge Electron Linear Accelerator (ORELA) (2) Transmission data of Harvey et al. /3/ for natural silicon measured on the 200-m flight path at ORELA (3) Total cross section data of Larson et al. /4/, measured on the 80- and 200-m flight paths at ORELA (4) 29Si-oxide /5/ and 30Si-oxide /6/ transmission data of Harvey et al., measured on the 80-m ORELA flight path (5) Elastic scattering thermal cross section for 30Si 2.490+-0.169 barns from Mughabghab /7/. Capture thermal cross section 0.107+-0.003 barns from Raman et al. /8/. Values given by resonance parameters are 2.500 and 0.107 barns respectively. ------------------------------------------------------------ Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 2.6066E+00 Elastic 2.4996E+00 n,gamma 1.0709E-01 5.8256E-01 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with TNG /9/. MT= 2 Elastic scattering cross section Obtained by subtracting non-elastic cross sections from total cross sections. MT= 4,51-91 (n,n') cross section Calculated with TNG code /9/. MT= 16 (n,2n) cross section Calculated with TNG code /9/. MT= 17 (n,3n) cross section Calculated with TNG code /9/. MT= 22 (n,na) cross section Calculated with TNG code /9/. MT= 28 (n,np) cross section Calculated with TNG code /9/. MT=102 Capture cross section Calculated with TNG code /9/. MT=103 (n,p) cross section Calculated from MT=600-649. MT=107 (n,a) cross section Calculated from MT=800-849. MT=600-649 partial (n,p) cross section Calculated with TNG code /9/. Comparing with experimental data, the calculations were multiplied by 1.5. MT=800-849 partial (n,a) cross section Calculated with TNG code /9/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with TNG code /9/. The shape elastic scattering component was calculated using OPTMAN code./10/ MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Neutron and gamma-ray spectra calculated with TNG/9/. MT= 17 (n,3n) reaction Neutron spectra calculated with TNG/9/. The gamma-ray spectra are not included, since the gamma-ray channel is not open below 20 MeV. MT= 22 (n,na) reaction Neutron, alpha-particle, and gamma-ray spectra calculated with TNG/9/. MT= 28 (n,np) reaction Neutron, proton, and gamma-ray spectra calculated with TNG/9/. MT= 51-72 (n,n') reaction Neutron angular distributions and discrete gamma-ray spectra calculated with TNG/9/. MT= 91 (n,n') reaction Neutron spectra, and discrete-continuous gamma-ray spectra calculated with with TNG/9/. MT=102 (n,gamma) reaction Gamma-ray spectra calcualted with TNG/9/. MT=600-605 (n,p) reactions leading to discrete levels Proton angular distributions and discrete gamma-ray spectra calculated with TNG/9/. MT=649 (n,p) reaction leading to continuum levels Proton spectra and discrete-continuous gamma-ray spectra calculated with TNG/9/. MT=800-828 (n,a) reactions leading to discrete levels Alpha-particle angular distributions and gamma-ray spectra calculated with TNG/9/. MT=849 (n,a) reaction leading to continuum levels Alpha-particle spectra and discrete-continuous gamma-ray spectra calculated with TNG/9/.*************************************************************** * Nuclear Model Calculations with TNG Code /9/ * *************************************************************** The description of the model calcualtions is given in Ref.10. < Optical model parameters > Neutrons and protons: Coupled-channel optical model parameters /10/ Alphas: The potential parameters were obtained using the code developed by Kumar and Kailas./11/ < Level scheme of Si- 30 > ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 0 + 1 2.23530 2 + 2 3.49860 2 + 3 3.76960 1 + 4 3.78790 0 + 5 4.80920 2 + 6 4.83080 3 + 7 5.23070 3 + 8 5.28000 4 + 9 5.37200 0 + 10 5.48750 3 - 11 5.61290 2 + 12 5.95020 4 + 13 6.50330 4 - 14 6.53700 2 + 15 6.64140 2 - 16 6.64200 0 + 17 6.74430 1 - 18 6.86500 3 + 19 6.91500 2 + 20 7.00100 5 + 21 7.04350 5 - 22 7.07900 3 + The direct-reaction process was taken into accout for the 1st and 8th excited levels by the coupled-channel method. < Level density parameters > Energy dependent parameters of Mengoni-Nakajima /13/ were used. ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Econt 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- Si- 31 5.408 2.155 -0.972 1.404 1.594 6.734 3.874 Si- 30 4.746 4.382 -2.125 2.139 0.450 15.991 7.223 Si- 29 5.138 2.228 -3.404 1.964 0.625 10.099 7.521 Si- 28 4.489 4.536 -4.401 2.454 1.949 15.409 8.819 Al- 30 4.764 0.000 0.148 1.663 -1.834 7.500 1.822 Al- 29 4.389 2.228 -0.301 1.949 -0.848 11.832 4.656 Mg- 27 4.864 2.309 -0.159 1.676 0.350 9.955 5.909 Mg- 26 4.228 4.707 -0.673 2.239 -0.005 17.464 7.200 ---------------------------------------------------------- References 1) L.C. Leal et al., Proc. Int. Conf. Nuclear Data for Science and Technology, Trieste, 1997, Part I, 929 (1997). 2) F.G. Perey, T.A. Love, W.E. Kinney, Oak Ridge National Laboratory report ORNL-4823 [ENDF-178] (1972). 3) J.A. Harvey, private communication (1996). 4) D.C. Larson, C.H. Johnson, J.A. Harvey, and N.W. Hill, "Measurement of the neutron total cross section of silicon from 5 eV to 730 keV," Oak Ridge National Laboratory report ORNL/TM-5618 (1976) 5) J.A. Harvey, private communication (1996). 6) J.A. Harvey, W.M. Good, R.F. Carlton, et al., Phys.Rev.C 28, 24 (1983). 7) S.F. Mughabghab, M. Divadeenam, N.E. Holden, Neutron Cross Sections, Vol. 1, Neutron resonance parameters and thermal cross sections, Part A: Z=1-60, (Academic Press, NY, 1981). 8) S. Raman, et al., Phys.Rev.C 46, 972 (1992). 9) C.Y. Fu, ORNL/TM-7042 (1980); K. Shibata, C.Y. Fu, ORNL/TM- 10093 (1986). 10) E.Sh. Soukhovitski et al., JAERI-Data/Code 2005-002 (2005). 11) K. Shibata, S. Kunieda, J. Nucl. Sci. Technol., 45, 123 (2008). 12) A. Kumar, S. Kailas, a computer code contained in RIPL-2, Bhabha Atomic Research Center, private communication (2002). 13) A. Mengoni, Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994).