17-Cl- 35 JAEA EVAL-Oct20 N.Iwamoto DIST-DEC21 20201031 ----JENDL-5 MATERIAL 1725 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2020-09 Evaluated with CCONE code by N.Iwamoto 2020-10 Evaluated with CCONE code by N.Iwamoto 21-11 revised by O.Iwamoto (MF8/MT4) added 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 (R-matrix limited) : below 1.2 MeV Adopted resonance paramters were evaluated with R-matrix code SAMMY/1,2/. The evaluation details in Appendix A were taken from ENDF/B-VIII.0. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 6.5564E+01 Elastic 2.0989E+01 n,gamma 4.3611E+01 1.7921E+01 n,p 4.7917E-01 4.7215E-01 n,alpha 8.0009E-05 3.5947E-05 ---------------------------------------------------------- (*) 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 the sum of the partial cross sections from the total cross section. MT=4,51-91 (n,n') cross section Calculated with CCONE code /3/. MT= 11 (n,2nd) 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= 34 (n,nHe3) cross section Calculated with CCONE code /3/. MT= 41 (n,2np) cross section Calculated with CCONE code /3/. MT= 42 (n,3np) cross section Calculated with CCONE code /3/. MT= 45 (n,npa) 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/. The cross section of MT=103 was obtained by the sum of the partial cross sections, in which (n,p0) cross section was calculated from the resonance parameters. The (n,p0) cross section in the range of 0.97 to 1.2MeV were calculated with the virtual channel widths of proton which were set 0.4 for the 0.9998, 1.0285, 1.0854, 1.1320 and 1.1553MeV-resonacnes, and it was adjusted to the resonance cross sections at 0.97MeV. 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=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=113 (n,t2a) cross section Calculated with CCONE code /3/. MT=115 (n,pd) cross section Calculated with CCONE code /3/. MT=117 (n,da) 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= 11 (n,2nd) 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= 34 (n,nHe3) reaction Calculated with CCONE code /3/. MT= 41 (n,2np) reaction Calculated with CCONE code /3/. MT= 42 (n,3np) reaction Calculated with CCONE code /3/. MT= 45 (n,npa) 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=113 (n,t2a) reaction Calculated with CCONE code /3/. MT=115 (n,pd) reaction Calculated with CCONE code /3/. MT=117 (n,da) 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= 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= 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= 42 (n,3np) 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=113 (n,t2a) 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=117 (n,da) reaction Decay chain is given in the decay data file. MF=10 Nuclide production cross sections MT= 16 (n,2n) reaction Calculated with CCONE code /3/. MF=32 Covariances of Resonance Parameters MT=151 Adopted covariances of resonance paramters were evaluated with R-matrix code SAMMY/1,2/. The evaluation details in Appendix A were taken from ENDF/B-VIII.0. ------------------------------------------------------------------ nuclear model calculation with CCONE code /3/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./4/ modified proton : global OMP, A.J.Koning and J.P.Delaroche/5/ modified 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 : L.McFadden and G.R.Satchler/8/ modified * Level scheme of Cl-35 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 3/2 + 1 1.219290 1/2 + 2 1.763040 5/2 + 3 2.645740 7/2 + 4 2.693750 3/2 + 5 3.002300 5/2 + 6 3.162800 7/2 - 7 3.918490 3/2 + 8 3.943820 9/2 + 9 3.967500 1/2 + 10 3.979000 5/2 + 11 4.059120 3/2 - 12 4.111980 7/2 + 13 4.173440 5/2 - 14 4.177880 3/2 - 15 4.347820 9/2 - 16 4.624350 5/2 + 17 4.768820 7/2 - 18 4.839080 3/2 + 19 4.854400 3/2 + 20 4.881070 7/2 + 21 5.010090 3/2 + 22 5.157000 5/2 + 23 5.163210 7/2 - 24 5.215790 3/2 + 25 5.403500 1/2 - 26 5.407200 11/2 - 27 5.520000 1/2 + 28 5.586000 5/2 + 29 5.599690 3/2 + 30 5.633000 5/2 + 31 5.645000 7/2 + 32 5.654480 3/2 + 33 5.682900 3/2 - 34 5.723600 5/2 + 35 5.758000 1/2 + 36 5.805500 5/2 + 37 5.823000 9/2 + 38 5.926900 11/2 - ----------------------- * 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 --------------------------------------------------------- Cl-36 5.249 0.000 -1.639 1.775 -2.386 10.951 4.525 Cl-35 5.698 2.028 -1.964 1.696 -0.432 13.216 5.927 Cl-34 5.569 0.000 -2.891 1.890 -3.122 15.206 4.211 Cl-33 5.441 2.089 -2.199 1.811 -0.654 14.733 5.277 S-35 6.469 1.500 -0.580 1.301 -0.059 8.685 4.303 S-34 5.658 4.116 -1.359 1.760 0.523 16.248 6.954 S-33 5.435 2.089 -2.399 1.924 -1.573 17.172 5.719 S-32 5.311 4.243 -3.372 1.659 4.220 14.479 10.493 P-34 5.012 0.000 -1.060 1.536 -0.682 7.200 3.951 P-33 5.441 2.089 -1.433 1.564 0.770 10.892 6.182 P-32 6.886 2.000 -2.705 1.600 -1.277 16.245 4.711 P-31 5.181 2.155 -3.214 2.010 -0.831 18.584 6.828 P-30 5.049 0.000 -4.335 1.713 1.101 10.763 5.411 --------------------------------------------------------- * Gamma-ray strength functions for Cl-36 E1: hybrid model(GH)/11/ ER= 20.78 (MeV) EG= 8.55 (MeV) SIG= 48.12 (mb) M1: standard lorentzian model(SLO) ER= 12.42 (MeV) EG= 4.00 (MeV) SIG= 2.74 (mb) E2: standard lorentzian model(SLO) ER= 19.08 (MeV) EG= 5.68 (MeV) SIG= 0.84 (mb) ***************************************************************** Appendix A from ENDF/B-VIII.0 ***************************************************************** CL35,37 Resonance Parameter Evaluation Update, January, 2007. R. O. Sayer, K. H. Guber, L. C. Leal, N. M. Larson (ORNL) The updated ENDF format now permits the full generality of the Reich-Moore theory, including charged particle exit channels. Consequently, we have updated the ENDF evaluations by adding resonance parameters (RPs) to File 2, MT=151, and by including the corresponding RP covariance matrices in File 32, MT=151. The Reich-Moore format with LRF=3 and LCOMP=1 was utilized for CL37. The Reich-Moore Limited (LRF=7, LCOMP=2) format was used for CL35 because the proton exit channel is open (Q = +0.61522 MeV). The applicable energy range is 0.00001 eV to 1.2 MeV. Above 1.2 MeV, cross sections from the February 2000 ENDF evaluation are used. The Cl evaluations [1,2] were based on fits of many data sets with the SAMMY code [3]. In ref [2] we give detailed discussions of the analysis methods used to determine parameter values and uncertainties. For capture and neutron width uncertainties, for example, for each resonance several SAMMY calculations with different width values were overlaid with the data. Both the overlay plots and chi-squared changes with width variation were used to determine final uncertainties that were, in most cases, significantly larger than the SAMMY values. The RADCOP code [4] was used to generate both File 2 and File 32. At the time of the Cl evaluation, SAMMY did not incorporate the now available "Prior Uncertainty Parameter", or PUP procedure. Thus, some normalization and background uncertainties were not propagated properly through the sequential analysis of multiple data sets. Although uncertainties in resonance energies and widths are felt to be realistic, the uncertainties in computed cross sections in valleys between resonances were underestimated. Furthermore, since File 32 is limited by the current ENDF format to RP uncertainties and correlations, uncertainties in nuclear radii cannot be treated directly. These "normalization/background/radius" effects were represented approximately by adjusting the File 32 uncertainties for the external RPs and for selected resonances in the energy range of the evaluation. Since the resonance parameter representation does not include the direct capture (DC) part of the capture cross section, the DC component was included as a "background" 1/v cross section in File 3, sections 1 and 102. At E = 0.0253 eV, the CL35 (CL37) DC cross section is 0.16 (0.31) b, which is a small (large) fraction of the overall capture cross section of 43.60 (0.433) b. The upper energy limit for the DC cross section is estimated [2] to be 10 (100) keV for CL35 (CL37). The 1/v cross section was extended to 1.0 MeV to ensure continuity in the evaluation range. REFERENCES ---------- [1] R. O. Sayer, K. H. Guber, L. C. Leal, N. M. Larson, and T. Rauscher, ORNL/TM-2003/50, March, 2003. [2] R. O. Sayer, K. H. Guber, L. C. Leal, N. M. Larson, and T. Rauscher, Phys. Rev. C73, 044603 (2006). [3] N. M. Larson, ORNL/TM-9179/R7 (2006), ENDF-364/R1. [4] R. O. Sayer and D. Wiarda, Physor-2006, Vancouver, B. C., Canada (2006). ***************************************************************** References 1) R.O.Sayer et al., ORNL/TM-2003/50 (2003) 2) R.O.Sayer et al., Phys. Rev. C 73, 044603 (2006) 3) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 4) S.Kunieda 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, 2005 (2011) 8) L.McFadden and G.R.Satchler, Nucl. Phys. 84, 177 (1966) 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) 11) S.Goriely, Phys. Lett. B436, 10 (1998)