6-C - 13 JAEA EVAL-Apr21 N.Iwamoto,S.Kunieda DIST-DEC21 20210401 ----JENDL-5 MATERIAL 628 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-04 Fast neutron energy region evaluated with CCONE code by N.Iwamoto 21-04 Resonance region evaluated with AMUR code by S.Kunieda 21-11 revised by O.Iwamoto (MF8/MT27,101) added 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 21-12 JENDL-5rc1 revised by N.Iwamoto,S.Kunieda (MF33/MT1-107, MF34/MT2) Evaluated with AMUR and CCONE- KALMAN ****************************************************** * * * --- JENDL-5.0 --- * * * * Incident neutron data up to 200 MeV * * * ****************************************************** Data evaulation was performed with an R-matrix code AMUR/1,2/ in the resolved resonance region up to 10 MeV MeV. Experimental data fitted are as follows. (n,tot) : Cohn+ (1961)/3/, CS (n,tot) : Auchampaugh+ (1979)/4/, CS (n,n0) : Lane+ (1981)/5/, DA (n,n0-n3) : Resler+ (1989)/6/, DA (n,g) : Firestone+ (2016)/7/ at 0.0253 eV, CS note: The (n,g) cross-sections were estimated with Rich-Moore approx./8/ putting distant poles for p-waves (sudo resonance) to mimic direct process. The approach was necessary to obtain evaluation consistent with MACS by Wallner+/9/. New evaluations taken from AMUR analysis are compiled in (MF,MT)= Cross sections : (3,1),(3,2),(3,51-53),(3,102) Angular distribution : (4,2),(4,51-53) Cross section covariance : (33,1),(33,2),(33,51-53) References 1) S.Kunieda+, Nucl. Data Sheets 118:250 (2014). 2) S.Kunieda+, Nucl. Data Sheets 123:159 (2015). 3) H.O.Cohn+, Phys. Rev., 122:534 (1961). 4) G.F.Auchampaugh+, Nucl. Sci. Eng. 69:30, (1979). 5) R.O.Lane+, Phys. Rev. C, 23:1883 (1981). 6) D.A.Resler+, Phys. Rev. C, 39:766 (1989). 7) R.B.Firestone+, Phys. Rev. C, 93:054306 (2016). 8) C.W.Reich and M.S.Moore, Phys. Rev. 111:929-933 (1958). 9) A.Wallner+, Phys. Rev. C, 93:045803 (2016) ***** CCONE evaluation above 10 MeV ***** MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Scattering radius only Temporal data were included. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 4.36068E+00 Elastic 4.35917E+00 n,gamma 1.50793E-03 7.16011E-04 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /1/. MT= 2 Elastic scattering cross section Calculated with CCONE code /1/. MT=4,51-91 (n,n') cross section Calculated with CCONE code /1/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /1/. MT= 16 (n,2n) cross section Calculated with CCONE code /1/. MT= 22 (n,na) cross section Calculated with CCONE code /1/. MT= 28 (n,np) cross section Calculated with CCONE code /1/. MT=102 Capture cross section Calculated with CCONE code /1/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /1/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /1/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /1/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /1/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /1/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /1/. MT= 16 (n,2n) reaction Calculated with CCONE code /1/. MT= 22 (n,na) reaction Calculated with CCONE code /1/. MT= 28 (n,np) reaction Calculated with CCONE code /1/. MT=51-91 (n,n') reaction Calculated with CCONE code /1/. MT=102 Capture reaction Calculated with CCONE code /1/. MT=600-649 (n,p) reaction Calculated with CCONE code /1/. MT=650-699 (n,d) reaction Calculated with CCONE code /1/. MT=700-749 (n,t) reaction Calculated with CCONE code /1/. MT=800-849 (n,a) reaction Calculated with CCONE code /1/. 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= 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=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=107 (n,a) reaction Decay chain is given in the decay data file. MF=33 Covariances of neutron cross sections Covariances were given to all the cross sections by using AMUR and KALMAN code and the covariances of model parameters used in the cross-section calculations. MF=34 Covariances for Angular Distributions MT= 2 Elastic scattering Covariances were given only to P1 components. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : S. Kunieda et al./2/ proton : global OMP, A.J.Koning and J.P.Delaroche/3/ deuteron: folding OMP, A.J.Koning and J.P.Delaroche/3/ triton : folding OMP, A.J.Koning and J.P.Delaroche/3/ He-3 : folding OMP, A.J.Koning and J.P.Delaroche/3/ alpha : V.Avrigeanu/4/ * Level scheme of C-13 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 1/2 - 1 3.089440 1/2 + 2 3.684510 3/2 - 3 3.853810 5/2 + 4 6.864000 5/2 + 5 7.492000 7/2 + 6 7.547000 5/2 - 7 7.686000 3/2 + 8 8.200000 3/2 + 9 8.860000 1/2 - 10 9.499800 9/2 + 11 9.897000 3/2 - 12 10.460000 3/2 + 13 10.753000 7/2 - 14 10.818000 5/2 - 15 10.996000 1/2 + 16 11.080000 1/2 - 17 11.748000 3/2 - 18 11.848000 7/2 + 19 11.950000 5/2 + 20 12.106000 3/2 + 21 12.130000 5/2 - 22 12.140000 1/2 + ----------------------- * Level density parameters (Gilbert-Cameron model/5/) Energy dependent parameters of Mengoni-Nakajima/6/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- C-14 3.251 6.414 -2.353 2.815 3.103 26.816 11.900 C-13 2.649 3.328 -4.617 3.442 1.399 30.767 12.140 C-12 4.113 6.928 -5.786 2.398 6.852 30.342 11.828 B-13 2.649 3.328 1.793 2.846 -0.962 15.809 6.425 B-12 2.468 0.000 -1.732 3.555 -4.420 23.413 6.000 B-11 2.240 3.618 -2.058 3.865 -0.611 28.948 12.040 Be-10 2.171 7.589 0.680 3.862 1.050 28.429 10.570 Be-9 2.336 4.000 -2.081 4.082 -3.489 34.441 6.760 Be-8 1.835 8.485 -4.748 4.709 5.985 42.440 3.030 --------------------------------------------------------- * Gamma-ray strength functions for C-14 E1: enhanced generalized lorentzian model(EGLO)/7/ ER= 16.68 (MeV) EG= 3.10 (MeV) SIG= 7.50 (mb) ER= 25.87 (MeV) EG= 6.84 (MeV) SIG= 9.40 (mb) M1: standard lorentzian model(SLO) ER= 17.01 (MeV) EG= 4.00 (MeV) SIG= 2.00 (mb) E2: standard lorentzian model(SLO) ER= 26.14 (MeV) EG= 5.94 (MeV) SIG= 0.26 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) S. Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 3) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 4) V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 5) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 6) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 7) J. Kopecky et al., Phys. Rev. C 47, 312 (1993)