59-Pr-141 JNDC EVAL-Aug18 F.Minato DIST-DEC21 20200327 ----JENDL-5 MATERIAL 5925 -----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 84-10 Evaluation for JENDL-2 was made by JNDC FPND W.G./1/ 90-03 Modification for JENDL-3 was made/2/. 93-10 JENDL-3.2 was made by JNDC FPND W.G. ***** modified parts for JENDL-3.2 ******************** (2,151) Resolved resonance parameters *********************************************************** 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/3/ by F.Minato/4/. ***** modified parts for JENDL-5.0 ******************** Continuum parts above En=13.226 keV were revised. Calculation is performed assuming spherical shape of Pr-141. 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 region (below 13.226 keV) Unresolevd resonance region (13.226 keV - 100 keV) Resonance parameters are taken from the JENDL-4.0/5/. Resolved resonance parameters for MLBW formula (below 13.226keV) Resonance parameters were taken from JENDL-2/6/ and slightly modified. In the evaluation for JENDL-2, neutron widths were evaluated on the basis of Wynchank et al./7/, Morgenstern et al. /8/ and Taylor et al./9/ radiation widths were determined from capture areas measured by Taylor et al. For the levels whose capture aria was only the existing data, their neutron widths were deduced by assuming the average radiation width of 0.084+-0.024 eV. Scattering radius of 4.9 fm was adopted from Mughabghab et al /10/. For JENDL-3, parameters of a negative resonance were modified so as to reproduce the capture cross section of 11.5+-0.3 barns at 0.0253 eV/10/ and the total cross section measured by Zimmerman et al./11/ and Hickman/12/. Total spin J of some resonances was tentatively estimated with a random number method. For JENDL-3.2, these resonance parameters were modified so as to reproduce the capture area data measured at ORNL, by taking account of the correction factor of 1.0737 announced by Allen et al./13/. ************************************************************** For JENDL-4.0, total spin J of 1364- and 3928-eV levels were modified on the basis of Alfimenkov et al./14/ Average capture cross section of 11.47+-0.29 b at 0.0253 eV was obtained from experimental data/8,31-35/. The parameters of -30-eV level were modified to reproduce the average cross section and the elastic scattering of 2.71+-0.06 b/15/. ************************************************************** Unresolved resonance region : 13.226 keV - 100 keV *************************************************************** For JENDL-5.0, the unresolved resonance parameters were re-evaluated by the ASREP /16/ code so as to reproduce the total and capture cross sections in the energy region from 13.226 keV 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 1.41968e+1 Elastic 2.72009e+0 n,gamma 1.14767e+1 1.84019e+1 ----------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /3/. The background cross section of (n,a) reaction is given below En = 13.226 keV. MT= 2 Elastic scattering cross section Calculated with CCONE code /3/. MT= 3 Non-elastic cross section Calculated with CCONE code /3/. MT=4,51-91 (n,n') cross section Calculated with CCONE code /3/. MT= 16 (n,2n) cross section Calculated with CCONE code /3/. MT= 17 (n,3n) cross section Calculated with CCONE code /3/. MT= 22 (n,na) cross section Calculated with CCONE code /3/. MT= 24 (n,2na) cross section Calculated with CCONE code /3/. MT= 28 (n,np) cross section Calculated with CCONE code /3/. MT= 29 (n,n2a) cross section Calculated with CCONE code /3/. MT= 32 (n,nd) cross section Calculated with CCONE code /3/. MT= 33 (n,nt) cross section Calculated with CCONE code /3/. MT= 34 (n,nHe3) cross section Calculated with CCONE code /3/. MT= 41 (n,2np) cross section Calculated with CCONE code /3/. MT= 44 (n,n2p) cross section Calculated with CCONE code /3/. MT= 45 (n,npa) cross section Calculated with CCONE code /3/. MT= 50 unknown MT=50 cross section Calculated with CCONE code /3/. MT=102 Capture cross section Calculated with CCONE code /3/. Below 13.226 keV, the cross sections are calculated with the resolved resonance parameters given in JENDL-4.0/5/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /3/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /3/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /3/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /3/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /3/. 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 = 65 eV. MT=108 (n,2a) cross section Calculated with CCONE code /3/. MT=111 (n,2p) cross section Calculated with CCONE code /3/. MT=112 (n,pa) cross section Calculated with CCONE code /3/. MT=115 (n,pd) cross section Calculated with CCONE code /3/. MT=116 (n,pt) cross section Calculated with CCONE code /3/. MT=117 (n,da) cross section Calculated with CCONE code /3/. MT=155 (n,ta) cross section Calculated with CCONE code /3/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /3/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /3/. MT= 17 (n,3n) reaction Calculated with CCONE code /3/. MT= 22 (n,na) reaction Calculated with CCONE code /3/. MT= 24 (n,2na) reaction Calculated with CCONE code /3/. MT= 28 (n,np) reaction Calculated with CCONE code /3/. MT= 29 (n,n2a) reaction Calculated with CCONE code /3/. MT= 32 (n,nd) reaction Calculated with CCONE code /3/. MT= 33 (n,nt) reaction Calculated with CCONE code /3/. MT= 34 (n,nHe3) reaction Calculated with CCONE code /3/. MT= 41 (n,2np) reaction Calculated with CCONE code /3/. MT= 44 (n,n2p) reaction Calculated with CCONE code /3/. MT= 45 (n,npa) reaction Calculated with CCONE code /3/. MT= 50 unknown MT=50 reaction Calculated with CCONE code /3/. MT=51-91 (n,n') reaction Calculated with CCONE code /3/. MT=102 Capture reaction Calculated with CCONE code /3/. MT=108 (n,2a) reaction Calculated with CCONE code /3/. MT=111 (n,2p) reaction Calculated with CCONE code /3/. MT=112 (n,pa) reaction Calculated with CCONE code /3/. MT=115 (n,pd) reaction Calculated with CCONE code /3/. MT=116 (n,pt) reaction Calculated with CCONE code /3/. MT=117 (n,da) reaction Calculated with CCONE code /3/. MT=155 (n,ta) reaction Calculated with CCONE code /3/. MT=600-649 (n,p) reaction Calculated with CCONE code /3/. MT=650-699 (n,d) reaction Calculated with CCONE code /3/. MT=700-749 (n,t) reaction Calculated with CCONE code /3/. MT=750-799 (n,He3) reaction Calculated with CCONE code /3/. MT=800-849 (n,a) reaction Calculated with CCONE code /3/. 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= 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= 41 (n,2np) 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=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=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=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=182 (n,dt) 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 /3/. MT=108 (n,2a) reaction Calculated with CCONE code /3/. MT=112 (n,pa) reaction Calculated with CCONE code /3/. MF=10 Nuclide production cross sections MT= 24 (n,2na) reaction Calculated with CCONE code /3/. MT= 32 (n,nd) reaction Calculated with CCONE code /3/. MT= 41 (n,2np) reaction Calculated with CCONE code /3/. MT= 45 (n,npa) reaction Calculated with CCONE code /3/. MT=105 (n,t) reaction Calculated with CCONE code /3/. MT=117 (n,da) reaction Calculated with CCONE code /3/. MT=155 (n,ta) reaction Calculated with CCONE code /3/. MT=158 (n,nda) reaction Calculated with CCONE code /3/. MT=159 (n,2npa) reaction Calculated with CCONE code /3/. MT=192 (n,dHe3) reaction Calculated with CCONE code /3/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /3/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./17/ 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 . proton : A.J.Koning and J.P.Delaroche/18/ with some modifications; the depth of real volume potential = 53.0 MeV the d_2^p ansatz of imaginary surface potential = 0.08 deuteron: J.M.Lohr and W.Haeberli/19/ triton : F.D.Becchetti Jr and G.W.Greenlees/20/ with some modifications; the radius parameter = 1.55 A^1/3 fm the diffuseness parameter = 1.05 fm He-3 : F.D.Becchetti Jr. and G.W.Greenlees/21/ alpha : J.R.Huizenga and G.Igo/22/ * Level scheme of Pr-141 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 5/2 + 1 0.145440 7/2 + 2 1.117970 11/2 - 3 1.127000 3/2 + 4 1.292700 5/2 + 5 1.298720 1/2 + 6 1.435590 3/2 + 7 1.452460 7/2 + ----------------------- * Level density parameters (Gilbert-Cameron model/23/) Energy dependent parameters of Mengoni-Nakajima/24/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Pr-142 14.088 0.000 -0.433 0.886 -3.378 8.135 0.177 Pr-141 17.814 1.011 -1.224 0.550 0.246 4.279 1.452 Pr-140 16.321 0.000 -0.539 0.600 -1.027 3.774 0.630 Pr-139 17.261 1.018 0.319 0.595 -0.526 5.307 1.147 Ce-141 16.030 1.011 -1.073 0.661 -0.312 5.557 1.497 Ce-140 17.363 2.028 -1.943 0.668 0.525 7.032 2.629 Ce-139 17.261 1.018 -1.123 0.669 -0.812 6.271 1.347 Ce-138 17.159 2.043 -0.413 0.620 0.510 6.537 2.471 La-140 17.363 0.000 -1.413 0.596 -0.993 3.825 2.040 La-139 17.261 1.018 -2.220 0.706 -0.744 6.662 1.580 La-138 18.112 0.000 -1.496 0.621 -1.428 4.548 0.293 La-137 16.062 1.025 -0.450 0.703 -1.029 6.576 0.926 La-136 16.954 0.000 0.209 0.676 -2.361 5.647 0.403 La-135 16.852 1.033 0.811 0.598 -0.594 5.354 0.984 --------------------------------------------------------- * Gamma-ray strength functions for Pr-142 E1: standard lorentzian model(SLO) ER= 15.60 (MeV) EG= 4.20 (MeV) SIG= 230.00 (mb) ER= 6.50 (MeV) EG= 2.00 (MeV) SIG= 8.30 (mb) M1: standard lorentzian model(SLO) ER= 7.86 (MeV) EG= 4.00 (MeV) SIG= 3.15 (mb) E2: standard lorentzian model(SLO) ER= 12.08 (MeV) EG= 4.41 (MeV) SIG= 3.31 (mb) References 1) T.Aoki et al., Proc. Int. Conf. on Nuclear Data for Basic and Applied Science, Santa Fe., Vol. 2, p.1627 (1985). 2) M.Kawai et al., J. Nucl. Sci. Technol., 29, 195 (1992). 3) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 4) F.Minato, J. Nucl. Sci. Technol., 50, 873 (2013). 5) K.Shibata et al., J. Nucl. Sci. Technol. 48, 1 (2011). 6) Y.Kikuchi et al., JAERI-M 86-030 (1986). 7) S.Wynchank et al., Phys. Rev. 166, 1234 (1968). 8) J.Morgenstern et al., Nucl. Phys. A123, 561 (1969). 9) R.B.Taylor et al., Aust. J. Phys., 32, 551 (1979). 10) S.F.Mughabghab et al., "Neutron Cross Sections, Vol. I, Part A", Academic Press (1981). 11) R.L.Zimmerman et al., Nucl. Phys., A95, 683 (1967). 12) G.D.Hickman, Bull. Am. Phys. Soc., 10, 12 (ad3) (1965). 13) B.J.Allen et al., Nucl. Sci. Eng., 82, 230 (1982). 14) V.P.Alfimenkov et al., JINR-P3-81-404,8107 (1981). 15) S.F.Mughaghab, Atlas of Neutron Resonances, (2006). 16) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999) [in Japanese]. 17) S.Kunieda et al., J. Nucl. Sci. Tech. Vol. 44, 838 (2007). 18) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 19) J.M.Lohr and W.Haeberli, Nucl. Phys. A232,381(1974) 20) F.D.Becchetti Jr and G.W.Greenlees, Annual Report. (Minneapolis, MN:J.H.Williams Lab., University of Minnesota (1969). 21) F.D.Becchetti Jr. and G.W.Greenlees, Ann. Rept. J.H.Williams Lab., Univ. Minnesota (1969) 22) J.R.Huizenga and G.Igo, Nucl. Phys. 29,462 (1962) 23) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 24) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994)