60-Nd-144 JAEA+ EVAL-Dec09 N.Iwamoto,A.Zukeran,K.Shibata DIST-DEC21 20100119 ----JENDL-5 MATERIAL 6031 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 09-12 The resolved resonance parameters were evaluated by A.Zukeran,K.Shibata. The data above the resolved resonance region were evaluated and compiled by N.Iwamoto. 21-11 revised by O.Iwamoto (MF8/MT4,16,17,22,24,28,32,33,41,102-105,107) JENDL/AD-2017 adopted (MF8/MT106) added (MF10/MT24,32,41,103,105) JENDL/AD-2017 based MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resonance parameters Resolved resonance region (MLBW formula): below 12 keV Resonance parameters adopted in JENDL-3.1 were taken from JENDL-2/1/: resonance energies were taken from Tellier /2/ and Musgrove et al./3/ by adjusting to those of ref. /2/. Nneutron widths were taken from ref./2/, and radiation widths were deduced from the capture areas of Musgrove et al. For the resonances not measured by Tellier, neutron widths were estimated from the capture areas by assuming the average radiation widths of 0.047 eV for s-wave resonances and of 0.041 eV for p-wave ones. For the lowest 2 levels, the capture widths of Karzhavina et al./4/ were adopted. A negative resonance was added at -76 eV so as to reproduce the capture cross section of 3.8+-0.3 barns at 0.0253 eV /5/. For JENDL-3.2, the capture data measured at ORELA of ORNL were renormalized (factor = 0.967)/6/. The neutron width and/or the radiation width was revised to reproduce the renormalized capture area for each resonance above 2.6 keV. Effective scattering radius recommended in ref./7/ was adopted and parameters of the nagative level were adjusted to thermal cross sections/7/. In JENDL-4, the data for 2.8 - 19.9 keV were updated by considering the capture area and g*Gamma_n data obtained by Wisshak et al./8/ The resonance energies and angular momenta (L, J) remain unchanged from JENDL-3.3. When the derived radiation width became negative, another J value was assumed. Moreover, the parameters for 374 eV were replaced with the ones obtained by Barry et al./9/ The parameters for the negative resonance were re-adjusted so as to reproduce the thermla capture cross section recommended by Mughabghab./10/ Unresolved resonance region : 12.0 keV - 200.0 keV The unresolved resonance paramters (URP) were determined by ASREP code /11/ so as to reproduce the evaluated total and capture cross sections calculated with optical model code OPTMAN /12/ and CCONE /13/. The unresolved parameters should be used only for self-shielding calculation. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 4.5280e+00 Elastic 9.0222e-01 n,gamma 3.6257e+00 6.3033e+00 n,alpha 1.5628e-05 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Sum of partial cross sections. MT= 2 Elastic scattering cross section Obtained by subtracting non-elastic scattering cross sections from total cross section. MT= 4 (n,n') cross section Calculated with CCONE code /13/. MT= 16 (n,2n) cross section Calculated with CCONE code /13/. MT= 17 (n,3n) cross section Calculated with CCONE code /13/. MT= 22 (n,na) cross section Calculated with CCONE code /13/. MT= 24 (n,2na) cross section Calculated with CCONE code /13/. MT= 28 (n,np) cross section Calculated with CCONE code /13/. MT= 32 (n,nd) cross section Calculated with CCONE code /13/. MT= 33 (n,nt) cross section Calculated with CCONE code /13/. MT= 41 (n,2np) cross section Calculated with CCONE code /13/. MT= 51-91 (n,n') cross section Calculated with CCONE code /13/. MT=102 Capture cross section Calculated with CCONE code /13/. MT=103 (n,p) cross section Calculated with CCONE code /13/. MT=104 (n,d) cross section Calculated with CCONE code /13/. MT=105 (n,t) cross section Calculated with CCONE code /13/. MT=106 (n,He3) cross section Calculated with CCONE code /13/. MT=107 (n,a) cross section Calculated with CCONE code /13/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with CCONE code /13/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /13/. MT= 17 (n,3n) reaction Calculated with CCONE code /13/. MT= 22 (n,na) reaction Calculated with CCONE code /13/. MT= 24 (n,2na) reaction Calculated with CCONE code /13/. MT= 28 (n,np) reaction Calculated with CCONE code /13/. MT= 32 (n,nd) reaction Calculated with CCONE code /13/. MT= 33 (n,nt) reaction Calculated with CCONE code /13/. MT= 41 (n,2np) reaction Calculated with CCONE code /13/. MT= 51-91 (n,n') reaction Calculated with CCONE code /13/. MT=102 Capture reaction Calculated with CCONE code /13/. ***************************************************************** Nuclear Model Calculation with CCONE code /13/ ***************************************************************** Models and parameters used in the CCONE calculation 1) Optical model * coupled channels calculation coupled levels: 0,1,2,3 (see Table 1) * optical model potential neutron omp: Kunieda,S. et al./14/ (+) proton omp: Koning,A.J. and Delaroche,J.P./15/ deuteron omp: Lohr,J.M. and Haeberli,W./16/ triton omp: Becchetti Jr.,F.D. and Greenlees,G.W./17/ He3 omp: Becchetti Jr.,F.D. and Greenlees,G.W./17/ alpha omp: McFadden,L. and Satchler,G.R./18/ (+) omp parameters were modified. 2) Two-component exciton model/19/ * Global parametrization of Koning-Duijvestijn/20/ was used. * Gamma emission channel/21/ was added to simulate direct and semi-direct capture reaction. 3) Hauser-Feshbach statistical model * Width fluctuation correction/22/ was applied. * Neutron, proton, deuteron, triton, He3, alpha and gamma decay channel were taken into account. * Transmission coefficients of neutrons were taken from optical model calculation. * The level scheme of the target is shown in Table 1. * Level density formula of constant temperature and Fermi-gas model were used with shell energy correction/23/. Parameters are shown in Table 2. * Gamma-ray strength function of generalized Lorentzian form /24/,/25/ was used for E1 transition. For M1 and E2 transitions the standard Lorentzian form was adopted. The prameters are shown in Table 3. ------------------------------------------------------------------ Tables ------------------------------------------------------------------ Table 1. Level Scheme of Nd-144 ------------------- No. Ex(MeV) J PI ------------------- 0 0.00000 0 + * 1 0.69656 2 + * 2 1.31467 4 + * 3 1.51087 3 - * 4 1.56092 2 + 5 1.79146 6 + 6 2.07291 2 + 7 2.08468 0 + 8 2.09328 5 - 9 2.10979 4 + 10 2.17897 3 + 11 2.18575 1 - 12 2.20480 4 - 13 2.21831 6 + 14 2.29541 4 + 15 2.32190 2 - 16 2.32818 0 + 17 2.34700 2 + 18 2.36882 2 + 19 2.39950 4 - 20 2.42021 5 + 21 2.45171 4 + 22 2.46400 1 - 23 2.49000 2 + 24 2.50842 3 - 25 2.52779 2 + 26 2.56451 3 + 27 2.58232 3 + 28 2.59000 1 - 29 2.59253 2 + 30 2.59900 3 - 31 2.60173 4 + 32 2.60300 3 + 33 2.60593 3 - 34 2.61307 7 - 35 2.61400 2 - 36 2.65510 3 + 37 2.65554 1 + 38 2.65600 4 + 39 2.67561 0 + 40 2.68167 3 - ------------------- *) Coupled levels in CC calculation Table 2. Level density parameters -------------------------------------------------------- Nuclide a* Pair Eshell T E0 Ematch 1/MeV MeV MeV MeV MeV MeV -------------------------------------------------------- Nd-145 18.5400 0.9965 1.1101 0.5235 -0.2928 4.6189 Nd-144 17.5000 2.0000 0.3419 0.6111 0.2496 6.6190 Nd-143 17.7000 1.0035 -0.4179 0.5516 0.0353 4.4179 Nd-142 15.0000 2.0140 -1.2557 0.6895 0.7987 6.4278 Pr-144 15.5000 0.0000 0.9153 0.6715 -1.9662 5.0412 Pr-143 16.6639 1.0035 0.4682 0.6161 -0.5920 5.4208 Pr-142 16.4000 0.0000 -0.4377 0.7390 -2.6336 6.4135 Pr-141 16.4637 1.0106 -1.2280 0.6590 -0.3966 5.5793 Ce-143 19.6000 1.0035 0.4100 0.4774 0.1189 3.9645 Ce-142 18.9500 2.0140 -0.3155 0.5558 0.6875 5.9346 Ce-141 17.9000 1.0106 -1.0773 0.4985 0.5829 3.4550 Ce-140 17.0742 2.0284 -1.9470 0.5674 1.4861 4.9920 Ce-139 15.5000 1.0178 -1.1255 0.5922 0.4151 4.0889 Ce-138 16.8661 2.0430 -0.4123 0.5781 1.0263 5.6162 -------------------------------------------------------- Table 3. Gamma-ray strength function for Nd-145 -------------------------------------------------------- * E1: ER = 14.95 (MeV) EG = 6.31 (MeV) SIG = 296.00 (mb) * M1: ER = 7.80 (MeV) EG = 4.00 (MeV) SIG = 1.05 (mb) * E2: ER = 11.99 (MeV) EG = 4.37 (MeV) SIG = 3.38 (mb) -------------------------------------------------------- References 1) Kikuchi, Y. et al.: JAERI-M 86-030 (1986). 2) Tellier, H.: CEA-N-1459 (1971). 3) Musgrove, A.R. de L., et al.: AEEC/E401 (1977). 4) Karzhavina, E.N., et al.: Sov. J. Nucl. Phys., 8, 371 (1969). 5) Fedorova, A.F., et al.: "Proc. 3rd All-union Conf. on Neutron Physics, Kiev 1975", Vol. 1, 169. 6) Allen, B.J. et al.: Nucl. Sci. Eng., 82, 230 (1982). 7) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I, Part A", Academic Press (1981). 8) Wisshak, K. et al.: Phys. Rev., C57, 3452 (1998). 9) Barry, D.P., et al.: Nucl. Sci. Eng., 153, 8 (2006). 10) Mughabghab, S.F: "Atlas of Neutron Resonances", Elsevier (2006). 11) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999) [in Japanese]. 12) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004). 13) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007). 14) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007). 15) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003) [Global potential]. 16) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974). 17) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept. J.H.Williams Lab., Univ. Minnesota (1969). 18) McFadden,L. and Satchler,G.R.: Nucl. Phys. 84, 177 (1966). 19) Kalbach,C.: Phys. Rev. C33, 818 (1986). 20) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004). 21) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985). 22) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980). 23) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151 (1994). 24) Kopecky,J., Uhl,M.: Phys. Rev. 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