7-N - 14 JNDC EVAL-JUN89 Y.KANDA(KYU) T.MURATA(NAIG)+ DIST-DEC21 20100317 ----JENDL-5 MATERIAL 725 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT HISTORY 89-06 New evaluation for JENDL-3 Sub-working group on evaluation of N-14, working group on nuclear data for fusion, Japanese Nuclear Data Committee In charge sig-t K.Shibata (jaeri) sig-el T.Asami (nedac), T.Murata (naig) sig-in T.Asami, T.Murata (n,2n),(n,p),(n,t),(n,a) Y.Kanda(kyu) (n,na),(n,ap),(n,nd),(n,d) T.Asami capture T.Asami photon production T.Asami Compilation Evaluated data were compiled by T.Fukahori (jaeri). 90-10 mf=5: Spectra were modified at low energies of emitted neutrons by T.Asami(Data Engineering, Co. ) 90-11 Reevaluation was made for the data concerning with the neutron emission double differential cross sections. The inelastic scattering cross sections and the angular distributions for the inelastically emitted neutrons were revised considerably/1/. 94-02 JENDL-3.2 mf=3, mt=1,2,4,22,32,52-90,103,105: cross section modified and mf=4, mt=54-90: isotoropic angular dist. added by T.Fukahori(jaeri). mf=12,mt=102: multiplicity modified by K.Shibata (jaeri). ***** Modified parts for JENDL-3.2 ********************** (3,1),(3,2) above 1 MeV (3,4),(3,22),(3,32) all energy region (3,52-71) 9-14 MeV (3,72) (3,72)+(3,73) of JENDL-3.1 (3,73) (3,74) of JENDL-3.1 (3,74-90) new pseud-level added (3,103) above 7 MeV (3,105) above 9 MeV (4,74-90) new pseud-level added (12,102) energy balance *********************************************************** 00-10 JENDL-3.3 The (n,p) cross sections were taken from JENDL Fusion File 99 /2/. The file was compiled by K.Shibata (jaeri). 01-07 JENDL-3.3 The (n,p) cross sections were modified between 10-5 eV and 40 keV. ***** Modified parts for JENDL-3.3 ********************** (1,451) Updated (3,1),(3,2) Re-calculated (3,103) Taken from JENDL Fusion File 99 Modified between 10-5 eV and 40 keV. (3,251) Deleted (4,2) Transformation matrix deleted (5,16-32) Modified *********************************************************** 09-08 JENDL-4.0 The data for MF/MT=12/103 were revised by K.Shibata (jaea). 10-01 (n,p) cross section was revised. 21-11 revised by O.Iwamoto (MF8/MT16,22,28,32,102-105,107,108) JENDL/AD-2017 adopted (MF8/MT4) added 21-11 above 20 MeV, JENDL-4.0/HE merged by O.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 21-12 (MF6/MT5) modified by O.Iwamoto ZAP=2003 DDX emission ene. rescaled near reaction threshold mf=1 General information mt=451 Descriptive data mf=2 Resonance parameters mt=151 Scattering radius only. mf=3 Cross sections calculated 2200 m/s cross sections and res. integ. 2200 m/s (b) res. integ. (b) total 11.905 - elastic 10.000 - capture 0.075 0.0034 mt=1 sig-t Below 1 eV, a sum of partial cross sections. Above 1 eV, based on the experimental data /3,4,5,6/. mt=2 sig-el Below 1 eV, sig-el = 10 barns. above 1 eV, the elastic scattering cross section was obtained by subtracting the reaction cross sections from the total cross section. mt=4 total inelastic Sum of mt=51 to 91. mt=16 (n,2n) Based on experimental data/7,8,9/. mt=22 (n,n alpha) Adopted the half of values calculated with the gnash code/10/. mt=28 (n,np) Calculated with the gnash code/10/, and normalized to the experimental data/11/. mt=32 (n,nd) Adopted the half of values calculated with the gnash code/10/. mt=51-90 sig-in The cross sections were calculated with the statistical model. The low-energy portion was analyzed with the resonance theory/12/. For mt=51 to 73, the direct components were calculated with the dwuck code/13/. For 74 to 90, pseud-levels were assumed and adjusted to fit to the experimental data/14/. The optical potential parameters used are the following /15/: V = 50.08-0.01E , Ws = 9.0 + 0.62E, Vso = 5.5 (MeV) r = 1.22 , rs = 1.45 , rso = 1.15 (fm) a = 0.66 , b = 0.13 , aso = 0.50 (fm). Level scheme no. energy(MeV) spin-parity g.s. 0.0 1 + 1. 2.3129 0 + 2. 3.9478 1 + 3. 4.9150 0 - 4. 5.1059 2 - 5. 5.6900 1 - 6. 5.8320 3 - 7. 6.2040 1 + 8. 6.4440 3 + 9. 7.0280 2 + 10. 7.9670 2 - 11. 8.0620 1 - 12. 8.4880 4 - 13. 8.6180 0 + 14. 8.7900 0 - 15. 8.91 3 - 16. 8.96 5 + 17. 9.13 3 + 18. 9.17 2 + 19. 9.51 2 - 20. 10.23 1 - 21. 10.81 5 + 22. 11.05 3 + 11.07 1 + (summing up) 23. 11.24 3 - 24. 11.5 (pseud-level) 25. 11.75 (pseud-level) 26. 12.0 (pseud-level) 27. 12.25 (pseud-level) 28. 12.5 (pseud-level) 29. 13.0 (pseud-level) 30. 13.5 (pseud-level) 31. 14.0 (pseud-level) 32. 14.5 (pseud-level) 33. 15.0 (pseud-level) 34. 15.5 (pseud-level) 35. 16.0 (pseud-level) 36. 16.5 (pseud-level) 37. 17.0 (pseud-level) 38. 17.5 (pseud-level) 39. 18.0 (pseud-level) 40. 18.5 (pseud-level) mt=102 Capture Calculated with the casthy code/16/. mt=103 (n,p) Below 7 MeV, based on experimental data/17,18,19,20,21, 22/. Above 7 MeV, based on experimental data/23/. For JENDL-3.3, the data were taken from FENDL-1 (BROND-2) above 6 MeV. The 1/v part was modified so as to reproduce a thermal cross section of 1.93 b mesured by Wagemans et al. /24/ mt=104 (n,d) Below 8.5 MeV, based on experimental data/25/. Above 8.5 MeV, calculated with gnash. mt=105 (n,t) Below 9 MeV, based on experimental data/26/. Above 9 MeV, based on experimental data/27,28/. mt=107 (n,alpha) Based on the experimental data/21,22,25,26/. mt=108 (n,2alpha) Calculated with gnash and normalized at 14.1 mev to an average value among the experimental data/29,30/. mt=800 (n, alpha0) Based on experimental data. mt=801 (n, alpha1) Based on experimental data. mt=849 (n, alpha) continuum Based on experimental data. mf=4 Angular distributions of secondary neutrons mt=2 1.e-5 eV to 8 MeV calculated with the resonance theory. 8 MeV to 20 MeV calculated with casthy. mt=16,22,28,32 Assumed to be isotropic in the center of mass system. The distributions were converted to the ones in the laboratory system. mt=51-73 Calculated with casthy/16/ and dwuck/13/. mt=74-90 Assumed to be isotropic in the center of mass system. mf=5 Energy distribution for secondary neutrons mt=16,22,28,32 Calculated with the gnash code/10/. mf=12 Photon production multiplicities mt=102,103 Calculated with the gnash code. for mt=102, modified by considering energy balance. mf=13 Photon production cross sections mt=3 Calculated with the gnash code/10/. mf=14 Photon angular distributions mt=3,102,103 Isotropic mf=15 Photon energy distributions mt=3,102,103 Calculated with the gnash code/10/. For mt=102, modified by using the experimental data/31/ at thermal energy. mf=33 Covariances for neutron cross sections mt=103 Below 60 keV, uncertainty of 3% /24/ was assumed. References 1) Kanda Y. et al.: JAERI-M 91-032 (1991) p.376. 2) Chiba S. et al.: Fusion Eng. Des., 37, 175 (1997). 3) Melkonian E.: Phys. 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