26-Fe- 57 JAEA EVAL-Jun21 N.Iwamoto DIST-DEC21 20210630 ----JENDL-5 MATERIAL 2634 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-06 Evaluated with CCONE code by N.Iwamoto 21-09 Secondary energy grids were added below 100keV by N.Iwamoto 21-10 Secondary energy grids were revised below 100keV by N.Iwamot 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resonance parameters Resolved resonance region: below 190 keV Resolved resonance parameters were taken from ENDF/B-VIII.0//1/. ------------------------------------------------------------ Comments for resonance evaluation in ENDF/B-VIII.0 ------------------------------------------------------------ The evaluation in the resonance region in based on the version of the Atlas that was still in development at the time our work was performed [3]. The compilation in the Atlas appeared to use parameters generated in Reich-Moore approximation. Because the Atlas also contained resonance parameters for resonances in the first (n,n) state, we decided to convert the Atlas compilation to the LRF=7 format using Reich-Moore approximation, including the first inelastic state. The change from MLBW Atlas parameters to LRF=7 parameters necessitated a refitting of the bound levels and R-prime. This change did improve agreement between the evaluation and experiment in the minima between resonances. The capture widths were known only from the area under each resonance. Additionally we added several resonances at the upper end of the RRR to improve agreement of the RRR with data in the region of 140-165 keV. The (n,n) resonances were determined by identifying capture resonances with no elastic counterpart and subtracting the capture width from the total width determined from (n,tot) measurements. The (n,n) resonances were assumed to be s-wave only. This choice was supported by the experimental results of Ref. [1] and Ref. [2]. Our thermal cross section and computed resonance integral values are in excellent agreement with the Atlas recommendations [3], as shown in the table below. Our MACS(30 keV) value lies roughly in between the JENDL-4.0 and KADoNiS-0.3 values and is generally consistent with the experimental averaged value given in the new Atlas. The Atlas value derived from systematics is more consistent with the KADoNiS-0.3 value. We note that the in-development version of KADoNiS-1.0 recommends a value basically taken from the Giubrone thesis [4], measured at CERN n-TOF. This measurement does not span the whole energy range of the resonance region. Therefore Giubrone omits several low energy resonances that would have provided a smooth background to the 30 keV region, lowering the MACS(30 keV) value obtained from the consideration of that set alone. Thus we use the MACS data for validation purposes only. Calculated 2200-m/s cross sections and res. integrals thermal res. integ. MACS (30 keV) total 3.087 b 94.48 b elastic 0.604 b 82.25 b capture 2.484 b 1.51 b 35.98 mb REFERENCES ---------- [1] G.Rohr and K.N.Muller, Untersuchungen an neutronen- resonanzen im 57Fe, Z. fuer Physik 227, 1 (1969). [2] S.Raman, G.G.Slaughter, W.M.Good, J.A.Harvey, J.B.McGrory, and D.Larson, 1- States in 58Fe, 277 (1974). 2nd Symp. on Neutr. Capt. Gamma Ray Spectrosc.,Petten 1974. [3] S.F.Mughabghab, Atlas of Neutron Resonances, Vol.1 and 2. Elsevier, Amsterdam (2018). [4] G.Giubrone, Neutron capture measurement of 54Fe and 57Fe at CERN n-TOF. PhD thesis, University of Valencia (2014). ------------------------------------------------------------ Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 3.09116E+00 Elastic 6.09271E-01 n,gamma 2.48184E+00 1.49362E+00 n,alpha 2.67795E-07 1.48115E-07 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /2/. MT= 2 Elastic scattering cross section Calculated with CCONE code /2/. MT=4,51-91 (n,n') cross section Calculated with CCONE code /2/. MT= 5 Total reaction (except fission) 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= 28 (n,np) cross section Calculated with CCONE code /2/. MT= 32 (n,nd) cross section Calculated with CCONE code /2/. MT= 41 (n,2np) cross section Calculated with CCONE code /2/. MT=102 Capture cross section Calculated with CCONE code /2/. 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/. 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/. 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= 5 Total reaction (except fission) 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= 28 (n,np) reaction Calculated with CCONE code /2/. MT= 32 (n,nd) reaction Calculated with CCONE code /2/. MT= 41 (n,2np) 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=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= 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= 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=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. ------------------------------------------------------------------ nuclear model calculation with CCONE code /2/ ------------------------------------------------------------------ * Optical model potentials neutron : A.J.Koning and J.P.Delaroche/3/ modified proton : global OMP, A.J.Koning and J.P.Delaroche/3/ deuteron: Y.Han et al./4/ triton : folding OMP, A.J.Koning and J.P.Delaroche/3/ He-3 : Y.Xu et al./5/ alpha : L.McFadden and G.R.Satchler/6/ * Level scheme of Fe-57 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 1/2 - 1 0.014410 3/2 - 2 0.136470 5/2 - 3 0.366760 3/2 - 4 0.706420 5/2 - 5 1.007130 7/2 - 6 1.139900 3/2 + 7 1.197810 9/2 - 8 1.265520 1/2 - 9 1.356830 7/2 - 10 1.627260 3/2 - 11 1.725380 3/2 - 12 1.976630 1/2 - 13 1.989660 9/2 - 14 1.991000 1/2 - 15 2.113110 5/2 - 16 2.118600 5/2 - 17 2.206880 5/2 - 18 2.217660 5/2 + 19 2.220200 7/2 - 20 2.330410 3/2 + 21 2.355960 11/2 - 22 2.358000 3/2 - 23 2.455550 9/2 + 24 2.456000 7/2 + 25 2.505290 5/2 + 26 2.564220 3/2 - 27 2.574500 1/2 - 28 2.593600 3/2 - 29 2.599400 3/2 + 30 2.697170 1/2 - 31 2.758300 1/2 + 32 2.821070 7/2 - 33 2.835890 7/2 - 34 2.855000 3/2 - 35 2.878700 13/2 - 36 2.904280 5/2 - 37 2.921200 3/2 - 38 2.970890 7/2 - 39 2.987950 5/2 + 40 3.059100 1/2 + ----------------------- * Level density parameters (Gilbert-Cameron model/7/) Energy dependent parameters of Mengoni-Nakajima/8/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Fe-58 7.852 3.151 -0.530 1.435 -1.487 14.731 4.348 Fe-57 8.315 1.589 -1.312 1.366 -2.315 12.701 3.059 Fe-56 8.265 3.207 -2.152 1.503 -1.634 17.526 4.683 Fe-55 8.333 1.618 -2.981 1.428 -1.607 14.443 3.860 Mn-57 8.634 1.589 0.838 1.058 -0.959 8.072 2.848 Mn-56 8.088 0.000 -0.645 1.291 -3.292 9.240 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 Cr-56 8.265 3.207 1.573 0.986 1.223 8.515 4.284 Cr-55 9.777 1.618 0.422 0.817 0.473 6.002 3.183 Cr-54 9.675 3.266 -0.310 1.049 0.511 10.460 4.256 Cr-53 7.868 1.648 -1.137 1.298 -1.087 10.541 3.435 Cr-52 7.792 3.328 -1.323 1.378 0.001 13.627 4.100 --------------------------------------------------------- * Gamma-ray strength functions for Fe-58 E1: hybrid model(GH)/9/ ER= 16.61 (MeV) EG= 5.57 (MeV) SIG= 31.94 (mb) ER= 19.66 (MeV) EG= 7.69 (MeV) SIG= 63.87 (mb) M1: standard lorentzian model(SLO) ER= 10.59 (MeV) EG= 4.00 (MeV) SIG= 1.79 (mb) E2: standard lorentzian model(SLO) ER= 16.28 (MeV) EG= 5.41 (MeV) SIG= 1.28 (mb) References 1) D.A.Brown et al., Nucl. Data Sheets, 148, 1 (2018) 2) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 3) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 4) Y.Han et al., Phys. Rev. C 74,044615(2006) 5) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 (2011) 6) L.McFadden and G.R.Satchler, Nucl. Phys. 84, 177 (1966) 7) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 8) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 9) S. Goriely, Phys. Lett. B436, 10 (1998)