13-Al- 27 TIT,JAERI EVAL-MAR88 Y.HARIMA,H.KITAZAWA,T.FUKAHORI 88MITO, 473 DIST-MAY10 20090828 ----JENDL-4.0 MATERIAL 1325 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT =========================================================== The data were taken from JENDL-3.3. =========================================================== HISTORY 88-03 Evaluation was performed for JENDL-3 by Harima, Kitazawa (Tokyo Institute of Tech.) and Fukahori (jaeri). Details are given in ref./1/. 88-03 Compiled by Fukahori. 93-12 JENDL-3.2. Compiled by T.Nakagawa (ndc/jaeri) ***** Modified parts for JENDL-3.2 ******************** (3,2) (3,66-91) Taken from JENDL fusion file* (3,4), (3,51-70) Cross-section curves were smoothed. (4,16-28), (4,91) Taken from JENDL fusion file (5,16-91) Taken from JENDL fusion file (12,51-70), (12,102) *********************************************************** ------------------------------------------------------------- JENDL fusion file /2/ (as of Sep. 1993) Evaluated by B.Yu (ciae) and S.Chiba (ndc/jaeri) Compiled by B.Yu. Cross sections were mainly taken from JENDL-3.1, except for the (n,n') (mt=66 to 70) and (n,n') continuum (mt=91) reactions which were taken from the calculation with sincros-II/3/. Angular distributions of these levels were taken to be equal to that of mt=66 in JENDL-3. EDXs for mt=16, 22, 28 and 91 were replaced by the sincros-II calculation. mf=6 were created by f15tob program. Kumabe's systematics/4/ was used. The pre- compound/compound ratio was taken from the sincros-II calculation. Optical-model, level density and other parameters used in the sincros-II calculation are described in ref./3/. Level schemes were determined on the basis of ENDSF/5/. ------------------------------------------------------------- 00-10 Re-evaluated by K. Shibata (jaeri) for JENDL-3.3 Compiled by K. Shibata ***** Modified parts for JENDL-3.3 *************************** (1,1451) Updated (3,1),(3,2),(3,4) Re-calculated. (3,16) Yamamuro's calculations /15/ (3,61),(3,62),(3,63) DWBA calculations were added. (3,67),(3,70) DWBA calculations were added. (3,203),(3,207) Calcualted. (3,251) Deleted. (4,2) Transformation matrix deleted. (4,16),(4,22),(4,28) Deleted. (4,91) Deleted. (5,16-91) Deleted. (6,16-91) Taken from JENDL fusion file. *************************************************************** mf=1 General information mt=451 Descriptive data and dictionary mf=2 Resonance parameters: mt=151 Resolved resonances : 1.0e-5 eV - 0.21 MeV The resonance parameters were searched, using MLBW formula/6/. An initial guess of the parameters search was taken from ref. /7/. Calculated 2200-m/s cross sections and resonance integrals 2200-m/sec res. integ. elastic 1.414 b - capture 0.231 b 0.123 b total 1.645 b - mf=3 Neutron cross sections mt=1 Total cross section Between 0.21 and 20 MeV, the cross sections were obtained by an eye-guide so as to follow the experimental data. mt=2 Elastic scattering cross sections Obtained by subtracting partial cross sections from the total cross sections. mt=4,51-70,91 Inelastic scattering cross sections For JENDL-3.1, cross sections up to 17-th level were calculated with the statistical-model code casthy /8/ and the coupled- channel model code ecis /9/ or jupitor-1 /10/, taking account of competitive processes for neutron, proton, alpha-particle and gamma-ray emission/1/. The following levels/11/ were taken into account. no. energy(MeV) spin-parity g.s. 0.0 5/2 + 1. 0.8438 1/2 + 2. 1.0145 3/2 + 3. 2.2100 7/2 + 4. 2.7340 5/2 + 5. 2.9814 3/2 + 6. 3.0040 9/2 + 7. 3.6780 1/2 + 8. 3.9560 5/2 + 9. 4.0540 3/2 - 10. 4.4090 5/2 + 11. 4.5103 11/2 + 12. 4.5800 7/2 + 13. 4.8120 5/2 + 14. 5.1550 3/2 - 15. 5.2460 5/2 + 16. 5.4199 5/2 + 17. 5.4330 9/2 + Continuum levels were assumed above 5.6 MeV. Level density was calculated, using the Gilbert-Cameron formula. The level- density parameters were obtained from a cumulative plot of observed levels/1/. For JENDL-3.2, cross sections for mt's from 66 to 70 and conti- nuum inelastic were replaced with JENDL fusion file. These mt's correspond to the following levels. 16. 5.4199 5/2 + 17. 5.4328 5/2 + 18. 5.4384 5/2 + 19. 5.4998 7/2 + 20. 5.5507 3/2 + Above 5.6 MeV, cross sections were summed up as the continuum inelastic (mt=91). Several energy points were added to mt= 4, 51-70 in order to smooth their cross section curves. For JENDL-3.3, the direct process was considered /16/ by DWBA calculations for mt=61,62,63,67,70. mt=16 (n,2n) cross sections Re-calculated by the sincros-II code /17/. mt=22 (n,na) cross sections Calculated by the statistical model with the gnash code/1,12/. optical potential for alpha-particles was determined, using the dispersion theory /13/. mt=28 (n,np) cross sections Calculated by the statistical model with the gnash code/1,12/. mt=102 capture Calculated with the statistical-model code casthy/8/ and the direct-semidirect-model code hikari/14/. The statistical- model calculations were normalized to 0.6 mb at 0.6 MeV. mt=103 (n,p) cross sections Calculated by the statistical model with the gnash code/1,12/. mt=107 (n,a) cross sections Obtained by an eye-guide to follow observed values /15/. mt=111 (n,2p) cross sections Calculated by the statistical model with the gnash code/1,12/. mt=203 proton production Sum of mt=28 and 103. mt=207 alpha production Sum of mt=22 and 107. mf=4 Angular distributions of secondary neutrons mt=2 Calculated with the statistical-model code casthy /1,8/. mt=51-66 Incoherent sum of the statistical model and coupled-channel model calculations/1/. Calculated with casthy and ecis or jupitor-1. mt=67-70 Assumed to be the same as mt=66. mf=6 Energy-angle distributions of secondary particles mt=16,22,28,91,203,207 Taken from JENDL fusion file. mf=12 gamma-ray multiplicities (below 5.80993 MeV) mt=51-70 Multiplicities were calculated from transition probabilities. mt=102 Calculated from energy balance. mt=103,107 Calculated by using the gnash code/1,12/. mf=13 Gamma-ray production cross sections (above 5.80993 MeV) mt=3 Calculated by the statistical model and coupled-channel model, using the gnash code /12/ and the ecis /9/ or jupitor-1 code /10/. Branching ratios for transitions between discrete levels were taken from ref./3/. Gamma-ray transition strength in the continuum was calculated by the brink-axel giant resonance model for E1 transition and by the Weisskopf single-particle model for E2 and M1 transition/1/. mf=14 Gamma-ray angular distributions mt=3,51-70,102,103,107 Isotropic distribution was assumed. mf=15 Gamma-ray spectra mt=3,102,103,107 Calculated with the gnash code/1,12/ References 1) Kitazawa H. et al.: Proc. Int. Conf. Nuclear Data for Science and Technology, Mito, 1988, p.473, (1988). 2) Chiba S. et al.: JAERI-M 92-027, p.35 (1992). 3) Yamamuro N.: JAERI-M 90-006 (1990). 4) Kumabe I. et al.: Nucl. Sci. Eng., 104, 280 (1990). 5) ENSDF: Evaluated Nuclear Stracture Data File. 6) Nakagawa T.: JAERI-M 84-192 (1984). 7) Mughabghab S.F. et al.: "Neutron Cross Sections, Vol. 1 Part A", Academic Press (1981). 8) Igarasi S. and Fukahori T.: JAERI 1321 (1991). 9) Raynal J.: Computer Program ECIS79 for Coupled-Channel Calculations, 1979 (unpublished). 10) Tamura T.: Rev. Mod. Phys., 37, 679 (1965). 11) Endt P.M. and Van der Leun C.: Nucl. Phys., A310, 1 (1978). 12) Young P.G. and Arthur E.D.: LA-6947 (1977). 13) Kitazawa H. et al.: unpublished. 14) Kitazawa H.: Computer Program Hikari for Direct-Semidirect Capture Calculations, 1980 (unpublished). 15) Vonach H.: Nuclear Data Standards for Nuclear Measurements, IAEA Technical Reports Series no. 227 (1983). 16) Shibata K.: Private communication (2000). 17) Yamamuro N.: Private communication (2000).