59-Pr-143 EVAL-Aug18 F.Minato DIST-DEC21 20200327 ----JENDL-5 MATERIAL 5931 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2018-08 Evaluated with CCONE code by F.Minato 2020-10 Energies of discrete primary photons were corrected. MF= 1 General information MT=451 Descriptive data and directory History 90-03 New evaluation for JENDL-3 was completed by JNDC FPND W.G./1/. 10-03 JENDL-4.0 was made. Resoloved resonance parameters were evaluated by T.Nakagawa. Unresolved resonance parameters were evaluated by S.Kunieda. The LSSF=1 was applied. Compiled by S.Kunieda ***** modified parts for JENDL-4.0 ******************** (1,451) Updated. (2,151) Updated. (3,1) Re-calculated from partial cross sections. (3,2) Calculated from URP in lower energy range. (3,4) Re-calculated from partial cross sections. (3,102) Calculated from URP in lower energy range. *********************************************************** 18-08 Evaluated with CCONE code/2/ by F.Minato/3/. ***** modified parts for JENDL-5.0 ******************** Continuum parts above En=500 eV were revised. Calculation is performed assuming spherical shape of Pr-143. The cross section of (n,a) is extrapolated to 1e-5 eV. The background cross section is given in (n,tot) [MF3,MT1]. *********************************************************** MF= 2 Resonance parameters MT=151 Resolved and unresolved resonance parameters Resolved resonance parameters (MLBW; below 500 eV) Resonance parameters are taken from the JENDL-4.0/4/. ************************************************************* For JENDL-4.0, resonance energies and neutron widths were evaluated on the basis of experimental data of Anufriev et al./5/ Average capture width was assumed to be 100 meV. A negative resonance was assumed at -10 eV adjusting its parameters to the capture cross section of 89+-10 b at 0.0253 eV/6/. Scattering radius was assumed to be 6.0 fm. ************************************************************* Unresolved resonance region : 500 eV - 0.1 MeV *************************************************************** For JENDL-5.0, the unresolved resonance parameters were re-evaluated by the ASREP /6/ code so as to reproduce the total and capture cross sections in the energy region from 500 eV to 100 keV. The parameters should be used only for self-shielding calculations. *************************************************************** Thermal cross sections and resonance integrals at 300 K ----------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ----------------------------------------------------------- Total 9.35384e+1 Elastic 3.49901e+0 n,gamma 9.00392e+1 1.59501e+1 ----------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /2/. The background cross section of (n,a) reaction is given below En = 500 eV. MT= 2 Elastic scattering cross section Calculated with CCONE code /2/. MT= 3 Non-elastic cross section Calculated with CCONE code /2/. MT=4,51-91 (n,n') cross section Calculated with CCONE code /2/. MT= 11 (n,2nd) cross section Calculated with CCONE code /2/. MT= 16 (n,2n) cross section Calculated with CCONE code /2/. MT= 17 (n,3n) cross section Calculated with CCONE code /2/. MT= 22 (n,na) cross section Calculated with CCONE code /2/. MT= 24 (n,2na) cross section Calculated with CCONE code /2/. MT= 28 (n,np) cross section Calculated with CCONE code /2/. MT= 29 (n,n2a) cross section Calculated with CCONE code /2/. MT= 32 (n,nd) cross section Calculated with CCONE code /2/. MT= 33 (n,nt) cross section Calculated with CCONE code /2/. MT= 34 (n,nHe3) cross section Calculated with CCONE code /2/. MT= 41 (n,2np) cross section Calculated with CCONE code /2/. MT= 45 (n,npa) cross section Calculated with CCONE code /2/. MT= 50 unknown MT=50 cross section Calculated with CCONE code /2/. MT=102 Capture cross section Calculated with CCONE code /2/. Below 500 eV, the cross sections are calculated with the resolved resonance parameters given in JENDL-4.0/7/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /2/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /2/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /2/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /2/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /2/. The cross section at 0.0253 eV is extrapolated by taking the capture cross section multiplied by a factor of sigma(n,a)/sigma(n,g) at En = 500 eV. MT=108 (n,2a) cross section Calculated with CCONE code /2/. MT=111 (n,2p) cross section Calculated with CCONE code /2/. MT=112 (n,pa) cross section Calculated with CCONE code /2/. MT=115 (n,pd) cross section Calculated with CCONE code /2/. MT=116 (n,pt) cross section Calculated with CCONE code /2/. MT=117 (n,da) cross section Calculated with CCONE code /2/. MT=155 (n,ta) cross section Calculated with CCONE code /2/. MT=193 (n,He3a) cross section Calculated with CCONE code /2/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /2/. MF= 6 Energy-angle distributions of emitted particles MT= 11 (n,2nd) reaction Calculated with CCONE code /2/. MT= 16 (n,2n) reaction Calculated with CCONE code /2/. MT= 17 (n,3n) reaction Calculated with CCONE code /2/. MT= 22 (n,na) reaction Calculated with CCONE code /2/. MT= 24 (n,2na) reaction Calculated with CCONE code /2/. MT= 28 (n,np) reaction Calculated with CCONE code /2/. MT= 29 (n,n2a) reaction Calculated with CCONE code /2/. MT= 32 (n,nd) reaction Calculated with CCONE code /2/. MT= 33 (n,nt) reaction Calculated with CCONE code /2/. MT= 34 (n,nHe3) reaction Calculated with CCONE code /2/. MT= 41 (n,2np) reaction Calculated with CCONE code /2/. MT= 45 (n,npa) reaction Calculated with CCONE code /2/. MT= 50 unknown MT=50 reaction Calculated with CCONE code /2/. MT=51-91 (n,n') reaction Calculated with CCONE code /2/. MT=102 Capture reaction Calculated with CCONE code /2/. MT=108 (n,2a) reaction Calculated with CCONE code /2/. MT=111 (n,2p) reaction Calculated with CCONE code /2/. MT=112 (n,pa) reaction Calculated with CCONE code /2/. MT=115 (n,pd) reaction Calculated with CCONE code /2/. MT=116 (n,pt) reaction Calculated with CCONE code /2/. MT=117 (n,da) reaction Calculated with CCONE code /2/. MT=155 (n,ta) reaction Calculated with CCONE code /2/. MT=193 (n,He3a) reaction Calculated with CCONE code /2/. MT=600-649 (n,p) reaction Calculated with CCONE code /2/. MT=650-699 (n,d) reaction Calculated with CCONE code /2/. MT=700-749 (n,t) reaction Calculated with CCONE code /2/. MT=750-799 (n,He3) reaction Calculated with CCONE code /2/. MT=800-849 (n,a) reaction Calculated with CCONE code /2/. MF= 8 Information on decay data MT=4 (n,n') reaction Decay chain is given in the decay data file. MT= 11 (n,2nd) 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= 23 (n,n3a) 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= 25 (n,3na) 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= 29 (n,n2a) reaction Decay chain is given in the decay data file. MT= 30 (n,2n2a) 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= 34 (n,nHe3) reaction Decay chain is given in the decay data file. MT= 35 (n,nd2a) reaction Decay chain is given in the decay data file. MT= 36 (n,nt2a) 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= 42 (n,3np) reaction Decay chain is given in the decay data file. MT= 44 (n,n2p) reaction Decay chain is given in the decay data file. MT= 45 (n,npa) 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=109 (n,3a) 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. MT=113 (n,t2a) reaction Decay chain is given in the decay data file. MT=114 (n,d2a) reaction Decay chain is given in the decay data file. MT=115 (n,pd) reaction Decay chain is given in the decay data file. MT=116 (n,pt) reaction Decay chain is given in the decay data file. MT=117 (n,da) reaction Decay chain is given in the decay data file. MT=154 (n,2nt) reaction Decay chain is given in the decay data file. MT=155 (n,ta) reaction Decay chain is given in the decay data file. MT=158 (n,nda) reaction Decay chain is given in the decay data file. MT=159 (n,2npa) reaction Decay chain is given in the decay data file. MT=176 (n,2nHe3) reaction Decay chain is given in the decay data file. MT=182 (n,dt) reaction Decay chain is given in the decay data file. MT=183 (n,npd) reaction Decay chain is given in the decay data file. MT=184 (n,npt) reaction Decay chain is given in the decay data file. MT=189 (n,nta) reaction Decay chain is given in the decay data file. MT=191 (n,pHe3) reaction Decay chain is given in the decay data file. MT=192 (n,dHe3) reaction Decay chain is given in the decay data file. MT=193 (n,He3a) reaction Decay chain is given in the decay data file. MT=197 (n,3p) reaction Decay chain is given in the decay data file. MF= 9 Isomeric branching ratios MT=102 Capture reaction Calculated with CCONE code /2/. MT=108 (n,2a) reaction Calculated with CCONE code /2/. MF=10 Nuclide production cross sections MT= 16 (n,2n) reaction Calculated with CCONE code /2/. MT= 30 (n,2n2a) reaction Calculated with CCONE code /2/. MT= 35 (n,nd2a) reaction Calculated with CCONE code /2/. MT=113 (n,t2a) reaction Calculated with CCONE code /2/. MT=114 (n,d2a) reaction Calculated with CCONE code /2/. MT=155 (n,ta) reaction Calculated with CCONE code /2/. MT=158 (n,nda) reaction Calculated with CCONE code /2/. MT=159 (n,2npa) reaction Calculated with CCONE code /2/. MT=189 (n,nta) reaction Calculated with CCONE code /2/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /2/ ------------------------------------------------------------------ * Optical model potentials neutron : kuni59141(no reference) with some modifications; V_R^0 =-37.00, lambda_R=0.0094, W_D^DISP= 9.50, WID_D=13.20, V_SO_0=9.00, R_R = 1.20, a_R = 0.58, R_SO =1.35. (The same potential as Pr-141 is used) proton : A.J.Koning and J.P.Delaroche/8/ with some modifications; the depth of real volume potential = 53.0 MeV the d_2^p ansatz of imaginary surface potential = 0.08 (The same potential as Pr-141 is used) deuteron: J.M.Lohr and W.Haeberli/9/ triton : F.D.Becchetti Jr and G.W.Greenlees/10/ with some modifications; the radius parameter = 1.55 A^1/3 fm the diffuseness parameter = 1.05 fm (The same potential as Pr-141 is used) He-3 : F.D.Becchetti Jr. and G.W.Greenlees/11/ alpha : J.R.Huizenga and G.Igo/12/ * Level scheme of Pr-143 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 7/2 + 1 0.057360 5/2 + 2 0.298000 3/2 + 3 0.350620 3/2 + 4 0.490360 7/2 + 5 0.614220 5/2 + 6 0.721920 5/2 + 7 0.740260 1/2 + 8 0.787330 5/2 - 9 0.848420 7/2 + 10 0.937820 3/2 + ----------------------- * Level density parameters (Gilbert-Cameron model/13/) Energy dependent parameters of Mengoni-Nakajima/14/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Pr-144 16.882 0.000 0.921 0.558 -1.225 3.696 0.059 Pr-143 17.669 1.003 0.474 0.576 -0.490 5.144 0.938 Pr-142 16.021 0.000 -0.433 0.635 -1.298 4.289 1.263 Pr-141 17.814 1.011 -1.224 0.550 0.246 4.279 1.452 Ce-143 17.669 1.003 0.416 0.629 -1.082 6.101 1.220 Ce-142 17.567 2.014 -0.310 0.594 0.619 6.207 2.125 Ce-141 16.592 1.011 -1.073 0.600 0.083 4.725 2.243 Ce-140 17.363 2.028 -1.943 0.668 0.525 7.032 2.629 Ce-139 17.261 1.018 -1.123 0.440 1.035 2.631 2.251 La-142 17.567 0.000 -0.105 0.522 -0.787 3.064 0.666 La-141 17.465 1.011 -0.490 0.440 0.887 2.821 2.181 La-140 17.363 0.000 -1.413 0.777 -3.153 7.629 0.104 La-139 17.261 1.018 -2.220 0.706 -0.744 6.662 1.580 La-138 17.159 0.000 -1.496 0.598 -0.936 3.765 0.738 La-137 17.057 1.025 -0.450 0.562 0.101 4.462 1.723 --------------------------------------------------------- * Gamma-ray strength functions for Pr-144 E1: standard lorentzian model(SLO) ER= 13.65 (MeV) EG= 3.83 (MeV) SIG= 116.87 (mb) ER= 15.69 (MeV) EG= 5.00 (MeV) SIG= 233.75 (mb) M1: standard lorentzian model(SLO) ER= 7.82 (MeV) EG= 4.00 (MeV) SIG= 2.94 (mb) E2: standard lorentzian model(SLO) ER= 12.02 (MeV) EG= 4.38 (MeV) SIG= 3.28 (mb) References 1) M.Kawai et al., Proc. Int. Conf. on Nuclear Data for Science and Technology, Mito, p. 569 (1988). 2) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 3) F.Minato, J. Nucl. Sci. Technol., 50, 873 (2013). 4) K.Shibata et al., J. Nucl. Sci. Technol. 44, 838 (2007). 5) V.A.Anufrief et al, 1987 Kiev, Vol.2, p.229 (1987). 6) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999) [in Japanese]. 7) K.Shibata et al., J. Nucl. Sci. Technol. 48, 1 (2011). 8) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 9) J.M.Lohr and W.Haeberli, Nucl. Phys. A232,381(1974) 10) F.D.Becchetti Jr and G.W.Greenlees, Annual Report. (Minneapolis, MN:J.H.Williams Lab., University of Minnesota (1969). 11) F.D.Becchetti Jr. and G.W.Greenlees, Ann. Rept. J.H.Williams Lab., Univ. Minnesota (1969) 12) J.R.Huizenga and G.Igo, Nucl. Phys. 29,462 (1962) 13) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 14) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994)