86-Rn-211 JAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 8625 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-10 Evaluated with CCONE code by N.Iwamoto 21-11 JENDL-5rc1 revised by N.Iwamoto (MF1/MT452,456) added (MF4,5/MT18) converted from (MF6/MT18) and added 21-12 JENDL-5rc1 revised by N.Iwamoto (MF5/MT18) corrected 21-12 (MF8/MT18) added by O.Iwamoto MF= 1 General information MT=451 Descriptive data and directory MT=452 Number of Neutrons per fission MT=456 Number of prompt neutrons per fission MF= 2 Resonance parameters MT=151 Scattering radius only AP is assumed to be 8.12 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 8.63744E+00 Elastic 8.31114E+00 n,gamma 2.86009E-01 1.15140E+01 n,p 5.01466E-08 2.56609E-06 n,alpha 1.24253E-03 4.89770E-02 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /1/. MT= 2 Elastic scattering cross section Calculated with CCONE code /1/. MT= 4,51-91 (n,n') cross section Calculated with CCONE code /1/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /1/. MT= 16 (n,2n) cross section Calculated with CCONE code /1/. MT= 17 (n,3n) cross section Calculated with CCONE code /1/. MT= 18 Fission cross section Calculated with CCONE code /1/. MT= 22 (n,na) cross section Calculated with CCONE code /1/. MT= 24 (n,2na) cross section Calculated with CCONE code /1/. MT= 28 (n,np) cross section Calculated with CCONE code /1/. MT= 32 (n,nd) cross section Calculated with CCONE code /1/. MT= 33 (n,nt) cross section Calculated with CCONE code /1/. MT= 41 (n,2np) cross section Calculated with CCONE code /1/. MT=102 Capture cross section Calculated with CCONE code /1/. The thermal cross section was derived from Shibata/2/. Below 61.20 eV the 1/v cross section was assumed. MT=103,600-649 (n,p) cross section Calculated with CCONE code /1/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /1/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /1/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /1/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /1/. MT=108 (n,2a) cross section Calculated with CCONE code /1/. MT=111 (n,2p) cross section Calculated with CCONE code /1/. MT=112 (n,pa) cross section Calculated with CCONE code /1/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /1/. MT= 18 Fission reaction Isotropic distributions in the laboratory system were assumed. MF= 5 Energy distributions of secondary neutrons MT= 18 Prompt neutrons Calculated with CCONE code/1/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /1/. MT= 16 (n,2n) reaction Calculated with CCONE code /1/. MT= 17 (n,3n) reaction Calculated with CCONE code /1/. MT= 22 (n,na) reaction Calculated with CCONE code /1/. MT= 24 (n,2na) reaction Calculated with CCONE code /1/. MT= 28 (n,np) reaction Calculated with CCONE code /1/. MT= 32 (n,nd) reaction Calculated with CCONE code /1/. MT= 33 (n,nt) reaction Calculated with CCONE code /1/. MT= 41 (n,2np) reaction Calculated with CCONE code /1/. MT= 51- 91 (n,n') reaction Calculated with CCONE code /1/. MT=102 Capture reaction Calculated with CCONE code /1/. MT=108 (n,2a) reaction Calculated with CCONE code /1/. MT=111 (n,2p) reaction Calculated with CCONE code /1/. MT=112 (n,pa) reaction Calculated with CCONE code /1/. MT=600-649 (n,p) reaction Calculated with CCONE code /1/. MT=650-699 (n,d) reaction Calculated with CCONE code /1/. MT=700-749 (n,t) reaction Calculated with CCONE code /1/. MT=750-799 (n,He3) reaction Calculated with CCONE code /1/. MT=800-849 (n,a) reaction Calculated with CCONE code /1/. MF= 8 Information on decay data MT= 4 (n,n') reaction Decay chain is given in the decay data file. MT= 5 Total reaction (except fission) reaction Decay chain is given in the decay data file. MT= 16 (n,2n) reaction Decay chain is given in the decay data file. MT= 17 (n,3n) reaction Decay chain is given in the decay data file. MT= 22 (n,na) reaction Decay chain is given in the decay data file. MT= 24 (n,2na) reaction Decay chain is given in the decay data file. MT= 28 (n,np) reaction Decay chain is given in the decay data file. MT= 32 (n,nd) reaction Decay chain is given in the decay data file. MT= 33 (n,nt) reaction Decay chain is given in the decay data file. MT= 41 (n,2np) reaction Decay chain is given in the decay data file. MT=102 Capture reaction Decay chain is given in the decay data file. MT=103 (n,p) reaction Decay chain is given in the decay data file. MT=104 (n,d) reaction Decay chain is given in the decay data file. MT=105 (n,t) reaction Decay chain is given in the decay data file. MT=106 (n,He3) reaction Decay chain is given in the decay data file. MT=107 (n,a) reaction Decay chain is given in the decay data file. MT=108 (n,2a) reaction Decay chain is given in the decay data file. MT=111 (n,2p) reaction Decay chain is given in the decay data file. MT=112 (n,pa) reaction Decay chain is given in the decay data file. MF= 9 Isomeric branching ratios MT= 22 (n,na) reaction Calculated with CCONE code /1/. MT=108 (n,2a) reaction Calculated with CCONE code /1/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./3/ proton : global OMP, A.J.Koning and J.P.Delaroche/4/ deuteron: Y.Han et al./5/ triton : folding OMP, A.J.Koning and J.P.Delaroche/4/ He-3 : Y.Xu et al./6/ alpha : M.Avrigeanu and V.Avrigeanu/7/ * Level scheme of Rn-211 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 1/2 - 1 0.539900 5/2 - 2 0.833500 3/2 - 3 1.458200 9/2 - 4 1.577800 13/2 - 5 1.603000 17/2 - 6 1.724100 15/2 - 7 1.739000 11/2 - 8 1.960000 11/2 - 9 2.139530 19/2 - 10 2.172760 21/2 - 11 2.179000 9/2 + 12 2.675500 23/2 + ----------------------- * Level density parameters (Gilbert-Cameron model/8/) Energy dependent parameters of Mengoni-Nakajima/9/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Rn-212 24.485 1.648 -4.945 0.525 1.073 5.172 3.735 Rn-211 24.389 0.826 -4.848 0.524 0.236 4.355 2.676 Rn-210 24.293 1.656 -4.141 0.513 0.942 5.191 2.607 Rn-209 24.196 0.830 -3.592 0.506 0.027 4.371 2.238 At-211 24.389 0.826 -5.957 0.546 0.456 4.355 2.960 At-210 24.293 0.000 -5.862 0.546 -0.387 3.535 1.689 At-209 24.196 0.830 -4.984 0.528 0.291 4.321 1.660 At-208 24.100 0.000 -4.456 0.476 -0.278 2.670 1.090 At-207 24.003 0.834 -3.727 0.491 0.236 4.002 1.496 Po-210 24.293 1.656 -7.246 0.597 1.429 5.724 3.429 Po-209 24.196 0.830 -7.008 0.428 1.440 1.100 2.654 Po-208 24.100 1.664 -6.087 0.606 0.858 6.470 2.703 Po-207 24.003 0.834 -5.415 0.557 0.230 4.720 1.909 Po-206 23.906 1.672 -4.732 0.518 1.182 4.972 1.916 Po-205 23.809 0.838 -4.025 0.553 -0.221 5.115 1.168 Po-204 23.713 1.680 -3.426 0.499 0.967 5.022 2.376 --------------------------------------------------------- * Gamma-ray strength functions for Rn-212 E1: hybrid model(GH)/10/ ER= 13.66 (MeV) EG= 3.84 (MeV) SIG= 610.78 (mb) M1: standard lorentzian model(SLO) ER= 6.88 (MeV) EG= 4.00 (MeV) SIG= 1.15 (mb) E2: standard lorentzian model(SLO) ER= 10.57 (MeV) EG= 3.57 (MeV) SIG= 5.82 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) K.Shibata, J. Nucl. Sci. Technol., 51, 425 (2014) 3) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 4) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 5) Y.Han et al., Phys. Rev. C 74,044615(2006) 6) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 (2011) 7) M.Avrigeanu and V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 8) A.Gilbert and A.G.W.Cameron, Can. J. Phys, 43, 1446 (1965) 9) A.Mengoni and Y.Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 10) S.Goriely, Phys. Lett. B436, 10 (1998)