25-Mn- 55 JAEA EVAL-Jun21 N.Iwamoto DIST-DEC21 20210607 ----JENDL-5 MATERIAL 2525 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 19-10 Evaluated with CCONE code by N.Iwamoto 21-06 Made revision of inelastic scattering cross sections by N.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 21-12 JENDL-5rc1 revised by N.Iwamoto (MF32/MT151) changed (MF33/MT1-112, MF34/MT2) Evaluated with CCONE-KALMAN MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resonances Resolved resonance parameters (below 125 keV) Evalauted by Derrien et al. See Appendix A for detailed explanation. The data revised in JEFF-3.3 were adopted. Unresolved resonance region : 125 keV - 1 MeV The unresolved resonance paramters (URP) were determined by ASREP code /1/ so as to reproduce the evaluated total and capture cross sections calculated with optical model code CCOM /2/ and CCONE /3/. 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 1.55036E+01 Elastic 2.22964E+00 n,gamma 1.32736E+01 1.42315E+01 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /3/. MT= 2 Elastic scattering cross section Obtained by subtracting non-elastic scattering cross section from total cross section. MT=4,51-91 (n,n') cross section Calculated with CCONE code /3/. Revised partial cross sections to obtain better agreement with the benchmark of SEG experiments. MT= 5 Total reaction (except fission) 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= 32 (n,nd) cross section Calculated with CCONE code /3/. MT= 41 (n,2np) cross section Calculated with CCONE code /3/. MT=102 Capture cross section Calculated with CCONE code /3/. 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/. MT=111 (n,2p) cross section Calculated with CCONE code /3/. MT=112 (n,pa) 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= 5 Total reaction (except fission) reaction Calculated with CCONE code /3/. 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= 32 (n,nd) reaction Calculated with CCONE code /3/. MT= 41 (n,2np) 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=111 (n,2p) reaction Calculated with CCONE code /3/. MT=112 (n,pa) 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= 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= 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=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=32 Covariances of resonance parameters MT=151 Resolved resonances Evalauted by Derrien et al. See Appendix A for detailed explanation. The data revised in JEFF-3.3 were adopted. MF=33 Covariances of neutron cross sections Covariances were given to all the cross sections by using KALMAN code and the covariances of model parameters used in the cross-section calculations. Data below 125 keV were taken from JEFF-3.3. MF=34 Covariances for Angular Distributions MT= 2 Elastic scattering Covariances were given only to P1 components. ------------------------------------------------------------------ nuclear model calculation with CCONE code /3/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./4/ proton : global OMP, A.J.Koning and J.P.Delaroche/5/ deuteron: Y.Han et al./6/ triton : folding OMP, A.J.Koning and J.P.Delaroche/5/ He-3 : Y.Xu et al./7/ alpha : V.Avrigeanu/8/ * Level scheme of Mn-55 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 5/2 - 1 0.125950 7/2 - 2 0.984260 9/2 - 3 1.289100 11/2 + 4 1.292110 11/2 - 5 1.293000 1/2 - 6 1.528350 3/2 - 7 1.884090 7/2 - 8 2.015200 7/2 - 9 2.198430 7/2 - 10 2.215000 5/2 - 11 2.252460 3/2 - 12 2.266810 5/2 - 13 2.281000 1/2 + 14 2.311450 13/2 - 15 2.365830 5/2 - 16 2.380000 3/2 - 17 2.398400 9/2 - 18 2.426520 1/2 + 19 2.563160 3/2 - 20 2.582000 1/2 + 21 2.621700 1/2 + 22 2.694600 7/2 + 23 2.727310 7/2 - 24 2.741000 7/2 + 25 2.752700 5/2 - 26 2.822100 9/2 - 27 2.823660 9/2 - 28 2.828440 7/2 - 29 2.873280 1/2 - 30 2.925000 3/2 - 31 2.953420 3/2 - 32 2.976180 3/2 - 33 2.984000 3/2 + 34 2.991770 7/2 - 35 3.005820 3/2 - 36 3.028000 3/2 - 37 3.035920 11/2 - 38 3.037360 1/2 - 39 3.039900 5/2 + 40 3.046000 5/2 - ----------------------- * Level density parameters (Gilbert-Cameron model/9/) Energy dependent parameters of Mengoni-Nakajima/10/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Mn-56 8.265 0.000 -0.645 1.254 -3.129 8.853 1.780 Mn-55 8.148 1.618 -1.124 1.431 -3.019 13.792 3.046 Mn-54 8.029 0.000 -2.202 1.328 -2.367 9.675 2.715 Mn-53 7.911 1.648 -2.189 1.436 -1.739 13.492 3.898 Cr-55 8.962 1.618 0.422 0.947 -0.023 6.689 3.183 Cr-54 8.029 3.266 -0.310 1.331 -0.678 13.189 4.256 Cr-53 7.911 1.648 -1.137 1.288 -1.049 10.441 3.435 Cr-52 7.792 3.328 -1.323 1.378 0.001 13.627 4.100 V-54 8.029 0.000 0.824 1.126 -2.625 6.760 0.968 V-53 7.911 1.648 0.712 1.082 -0.411 7.587 3.158 V-52 7.792 0.000 -0.616 1.248 -2.564 7.963 0.881 V-51 7.672 1.680 -0.648 1.442 -2.775 13.024 3.663 V-50 7.552 0.000 -0.638 1.227 -2.107 7.216 2.597 --------------------------------------------------------- * Gamma-ray strength functions for Mn-56 E1: modified lorentzian model(MLO1)/11/ ER= 16.65 (MeV) EG= 5.60 (MeV) SIG= 27.29 (mb) ER= 19.90 (MeV) EG= 7.86 (MeV) SIG= 54.58 (mb) M1: standard lorentzian model(SLO) ER= 10.72 (MeV) EG= 4.00 (MeV) SIG= 2.89 (mb) E2: standard lorentzian model(SLO) ER= 16.47 (MeV) EG= 5.44 (MeV) SIG= 1.22 (mb) References 1) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999) [in Japanese]. 11) V.A. Plujko et al., J. Nucl. Sci. Technol.(supp. 2), 811 (2002) 2) O.Iwamoto, JAERI-Data/Code 2003-020 (2003) 3) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 4) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007) 5) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 6) Y.Han et al., Phys. Rev. C 74,044615(2006) 7) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 (2011) 8) V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 9) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 10) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) ================================================================== Appendix A: Resolved resonance parameters ================================================================== EVALUATION of the RESONANCE PARAMETERS of Mn-55 in the ENERGY RANGE 0 to 122 keV- H. Derrien, L.C. Leal, N.M.Larson, D. Wiarda K. Guber, and G. Arbanas. The resonance parameters were obtained from a sequential Bayes SAMMY analysis of the most recent experimental neutron transmissions and capture cross sections in the resolved energy range: Harvey et al. transmissions measured at ORELA in 1980, Aerts et al. Capture cross sections measured at GELINA in 2006, and Guber et al. Capture cross section measured at ORELA in 2007. For the evaluation in the thermal energy range Widder et al. (1975) capture cross section, Cote et al. (1964) total cross sections, and Rainwater et al. (1964) total cross sections were considered. The thermal capture cross sections were normalized at the 0.0253 eV value of 13.27 b which is an average of the available experimental values, consistent with the recent evaluation of Trkov et al.(2007). The thermal cross sections calculated by the resonance parameters are the following: Res. Int. Capture 13.274 b 13.514 Total 15.390 b - Scattering 2.116 b - The capture resonance integral is 13.516 b in the energy range 0.5 eV to 120 keV. Most of the p-wave resonances are not observed in the experimental transmission data. For those resonances only the capture area could be obtained with good accuracy. The capture area is proportional to gamman*gammag / gammatot and only the product gamman*gammag could be defined. A solution is to assign to all this resonances a constant capture width value equal to an estimated averaged value. In this case the SAMMY fit to the capture data is generally poor. The solution of varying both the capture width and the neutron width in the SAMMY fit has been chosen is the evaluation. The resulting capture widths do not deviate too much from an average value. The fit is obviously not unique but give a good description of the experimental data. The study of the statistical properties of the neutron widths has shown that the obtained set of parameters is reasonable. Only s-wave and p-wave resonances are given in the evaluation. However the study of the statistical properties of the p-wave resonance parameters has shown that 25% of them(the very small one) could be d-wave resonances. Including these possible d-wave resonances in the p-wave resonances has a negligible effect on the calculated capture cross section. Two components of the capture cross section are given in the evaluation: the first component is calculated by the observed resonance parameters; the second component is given as a File 3 background. This background stands for the contribution of the the contribution of the direct capture, for the contribution of non observed d-wave resonances, and for possible errors in the errors in the calculation of the multiple scattering effect by SAMMY in the experimental capture cross sections. The estimation of the average d-wave contribution below 122 keV was obtained from SAMMY/URR. The error on the background file is important (20% to 30%), contributing to the most part of the uncertainty on the average captur cross section The following Table compares the average capture cross section to the experimental values of Lerigoleur , and of Garg and Macklin. The present evaluation is systematically lower than Lerigoleur (absolute measurement) by 12% on average; part of the discrepancy could be due to the inaccuracy of the calculation of the d-wave component in the background file. ___________________________________________________________ Energy Range Present Results Lerigoleur Garg-Macklin keV mb mb Mb ___________________________________________________________ 15 - 20 47.98+/12/-4.56 48.6 20 - 30 35.79+/13/-3.28 44.6 30 - 40 25.24+/14/-2.19 44.7 40 - 50 25.24+/15/-1.57 28.2 50 - 60 20.40+/16/-1.63 26.0 60 - 80 16.69+/17/-1.61 21.5 80 -100 15.00+/18/-1.41 16.3 100 -120 11.63+/19/-1.41 14.3 ___________________________________________________________ Resonance parameter covariance was generated in the resolved energy region (1.0-5 eV to 125 keV) with the computer code SAMMY at ORNL. Experimental data and uncertainties were used to generate covariance data. SAMMY covariance information was converted in the ENDF FILE32 representation. The covariance information was processed with the PUFF-IV code. The details of the evaluation are in progress of publication in an ORNL/TM report. References: HA 90 Harvey, private communication, 2007 AE 06, private communication 2006 GU 07 Guber, to be published, 2007 WI 75, Wilder, R_EIR-217, 1975 CO 64, Cote, PR/B, 134, 1047, 1964 RA 64, Rainwater, RSI, 35, 263, 1964 TR 07, private communication 2007 LE 76, Lerigoleur CEA-R-4888, 1976 GA 78, Garg-Macklin, PR/C, 18, 2079, 1978 ==================================================================