8-O - 16 JNDC EVAL-DEC83 Y.KANDA(KYU) T.MURATA(NAIG)+ JAERI-M 90-012 DIST-MAY10 20090629 ----JENDL-4.0 MATERIAL 825 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT HISTORY 83-12 New evaluation for JENDL-3 Sub-working group on evaluation of O-16, Working group on nuclear data for fusion, Japanese Nuclear Data Committee In charge sig-t Y.Nakajima K.Shibata(jaeri) sig-el T.Murata(naig) sig-in S.Tanaka(jaeri) capture T.Asami(jaeri) (n,2n),(n,p),(n,d),(n,alpha) Y.Kanda(kyu) Compilation Evaluated data were compiled by K.Shibata. 84-07 Data of mf=4 (mt=16,91) were revised. Comment was also modified. 87-01 Data of mf=3 (mt=51-64,67), mf=4 (mt=51-55) and mf=5(mt=16) were modified (S.Chiba, jaeri). Comment was also modified. 90-10 mf=5 (except mt=91), mf=12, mt=102 modified. 93-12 Capture and gamma production cross sections were modified. 08-07 Total and elastics scattering cross sections were modified below 3 MeV. The elastic angular distributions were replaced with new R-matrix calculations between 100 keV and 3 MeV. 09-04 The (n,a) cross sections was modified. 09-06 The interpolation of MF/MT=12/102 was changed to 2. ***** modified parts for JENDL-3.2 ****************************** (3,102) Reevaluated by K. Shibata. (3,2),(3,3) Recalculated (12,102) Modified due to energy conservation (12,51;57;62) 510 keV gammas incorporated (13,3) Reevaluated by T. Asami (de) ****************************************************************** ***** modified parts for JENDL Fusion File 96/1/26 ************* (3,102) Calculated by A. Mengoni (enea) (3,2),(3,3) Recalculated ****************************************************************** 2002-1 Compiled by K.Shibata (jaeri) for JENDL-3.3. ***** modified parts for JENDL-3.3 2001/5/23 ******************* (1,451) Modified. (3,1),(3,2) Recalculated (3,16) Corrected The JENDL-3.2 data were ten times larger than the measurement /2/ by mistake. (3,3) Deleted (3,251) Deleted (4,2) Transformation matrices were deleted. (5,22),(5,28) Distributions at threshold were modified. Interpolation was changed to 22. (12,51-107) Calculated. (13,3) Deleted. (14,51-107) Prepared. (15,3) Deleted. (15,51-107) Calculated. (33,1-107) Taken from JENDL-3.2 covariance file except for mt=16. The covariance for mt=16 was revised on the basis of experimental data. (34,2) Taken from JENDL-3.2 covariance file. ****************************************************************** 2009-04 Compiled by K.Shibata (jaea) for JENDL-4 ***** modifications for JENDL-4 2008/07/02 ********************* (1,451) Modified (3,2) R-matrix calculations below 3 MeV (3,1) Re-calculated from partial cross sections (4,2) R-matrix calculations between 100 keV and 3 MeV (3,107) The data were replaced with those of ENDF/B-VII.0 below 6.5 MeV. ****************************************************************** mf=1 General information mt=451 Descriptive data mf=2 Resonance parameters mt=151 Scattering radius only. mf=3 Cross sections Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 3.9624E+00 Elastic 3.9646E+00 n,gamma 1.8988E-04 6.7337E-04 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. mt=1 Sig-t Below 3 MeV, the total cross section was calculated with the R-matrix theory. Above 3 MeV, based on the experimental data of Cierjacks et al./1/. ********************************************************* For JENDL-4, data were modified below 3 MeV. See above. ********************************************************* mt=2 Sig-el Below 3 MeV, calculated with the R-matrix theory. Above 3 MeV, the elastic scattering cross section was obtained by subtracting the reaction cross sections from the total cross section. ********************************************************* For JENDL-4, data were modified below 3 MeV. See above. ********************************************************* mt=4 Total inelastic Sum of mt=51 to 91. mt=16 (n,2n) Based on experimental data/2/. mt=51-79,91 Sig-in Shape of the excitation functions was calculated with the statistical model. The optical potential parameters are the following: V = 48.25-0.053E, Ws = 3.0 + 0.25E, Vso = 5.5 (MeV) r = 1.255 , rs = 1.352 , rso = 1.15 (fm) a = 0.536 , b = 0.205 , aso = 0.50 (fm). Level scheme no Energy(MeV) Spin-parity g.s. 0.0 0+ 1 6.0490 0+ 2 6.1300 3- 3 6.9170 2+ 4 7.1169 1- 5 8.8720 2- 6 9.6300 1- 7 9.8470 2+ 8 10.360 4+ 9 10.960 0- 10 11.080 3+ 11 11.100 4+ 12 11.520 2+ 13 11.600 3- 14 12.050 0+ 15 12.440 1- 16 12.530 2- 17 12.800 0- 18 12.970 2- 19 13.020 2+ 20 13.090 1- 21 13.120 3- 22 13.260 3- 23 13.660 1+ 24 13.870 4+ 25 13.980 2- 26 14.030 0+ 27 14.100 3- 28 14.300 4+ 29 14.400 5+ Continuum levels were assumed above 14.4 MeV. Constant temperature of 3.4 MeV was used. For the inelastic scattering to the second and third levels, the (n,n')gamma data of Nordborg et al./3/ and Lundberg et al./4/ below 10 MeV. For mt=51 to 55, the 14 MeV cross sections were normalized to the experimental data/5/-/8/. Cross sections for mt=56-64 and 67 were normalized to reproduce the ddx data at 14 MeV/8/,/9/. mt=102 Capture 1/v curve normalized to the recommended value in the 4th edition of BNL-325 /10/ at 0.0253 eV. Between 1 eV and 1 MeV, model calculations (direct capture and resonance) were performed by A. Mengoni (enea)/28/. Above 1 MeV, a value of 0.1 mb was assumed by considering inverse reaction data. mt=103 (n,p) Based on experimental data/11/-/14/. mt=104 (n,d) Based on the evaluation of Foster, Jr. and Young /15/. mt=107 (n,alpha) Based on experimental data/3/,/16/-/21/. For JENDL-4, the measured (n,a) cross sections, which were coverted from the inverse-reaction data/18,21,32/, were compared with the existing libraries. As a result, it was found that the ENDF/B-VII.0 data reproduce the experimental data fairly well below 6.5 MeV. Therefore, we decided to replace the (n,a) data with those of ENDF/B-VII.0 below 6.5 MeV. Above 6.5 MeV, the cross sections remain unchanged from JENDL-3.3. mf=4 Angular distributions of secondary neutrons mt=2 10e-5 eV to 3 MeV R-matrix calculation 3 MeV to 5 MeV Based on the experimental data of Lister and Sayres /22/. 5 MeV to 9 MeV Multi-level formula/23/. 9 MeV to 15 MeV Based on the experimental data of Glendinning et al./24/ 15 MeV to 20 MeV Calculated with the spherical optical model. The potential parameters are the same as those given in Sig-in. ********************************************************* For JENDL-4, data were modified between 100 keV and 3 MeV. See above. ********************************************************* mt=16 Assumed to be isotropic in the laboratory system. mt=51-79 Calculated with the statistical model. For mt=51, 52 and 55, experimental data/8/ at 14.2 MeV. For mt=53 and 54 ENDF/B-IV was adopted. mt=91 Isotropic distributions in the center of mass system were transformed into the ones in the laboratory system. The formula is given in ref./25/. mf=5 Energy distribution for secondary neutrons mt=16 Evaporation spectrum was assumed. Constant temperature was deduced from the experimental data of Chiba et al. /26/ for Li-7 according to the Sqrt(E/a) law. mt=22,28 Calcualted by GNASH /27/. mt=91 Evaporation spectrum was assumed. Constant temperature of 3.4 MeV was determined from the stair case plotting. mf=12 Photon production multiplicities mt=22,51-55,59,61,63,66-68,103,107 Calculated with GNASH/27/. mt=102 Calculated with CASTHY/29/. Below 280 keV, based on the data measured by Igashira et al./30/ mf=14 Photon angular distributions mt=22,51-55,59,61,63,66-68,102,103,107 Isotropic mf=15 Photon energy distributions mt=22,103,107 Calculated with GNASH/27/. mt=102 Calculated with CASTHY/29/. mf=33 Covariances of cross sections (ref. 31) mt=1 Based on experimental data. A chi-value was 6.53. mt=2 Constructed from mt=1, 16, 22, 28, 51-91, 102, 103, 104, and 107. mt=4 Constructed from mt=51-91. mt=16 Based on experimental data. mt=22 Based on systematics. mt=28 Based on systematics. mt=51-91 The covariances were estimated by using kalman system. A chi-value was 2.45. For mt=52,53, based on experimental data between 7 and 11 MeV. mt=102 Based on experimental data. mt=103 Based on experimental data. mt=104 Based on experimental data. mt=107 Based on experimental data. mf=34 Covariances of angular distributions mt=2 Based on experimental data and model calculations. References 1) Cierjacks,S. et al.: Nucl. Instr. 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