16-S - 32 FUJI E.C. EVAL-MAY87 H.NAKAMURA DIST-MAY10 20090828 ----JENDL-4.0 MATERIAL 1625 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT =========================================================== The data were taken from JENDL-3.3. =========================================================== HISTORY 87-03 Newly evaluated by H.Nakamura (fuji electric co.ltd.) 88-08 The following quantities were modified by H.Nakamura: (n,p) cross section inelastic scattering cross sections and angular distributions of the first, third and continuum levels 94-02 JENDL-3.2 Coupled-channel calculation was performed by K. Shibata (jaeri) using the omp set determined by T. Watanabe (khi). the total and inelastic scattering cross sections were replaced by the c.c. calculations. Data were compiled by K. Shibata. ***** modified parts for JENDL-3.2 **************************** (3,1),(3,4),(3,51-56,91),(3,251),(4,2),(4,51-56) coupled-channel calculations. (3,2) total - nonelastic **************************************************************** 01-04 JENDL-3.3 Gamma-ray production data were evaluated and compiled by K. Shibata ***** modified parts for JENDL-3.3 **************************** (1,451) Updated (3,251) Deleted. (4,2) Transformation matrix deleted. (5,16-91) INT=22. (12,16-107) Added. (14,16-107) Added. (15,16-107) Added. **************************************************************** mf=1 General information mt=451 Descriptive data and dictionary mf=2 mt=151 Resonance parameters: Resolved resonances for MLBW formula: 1.0e-5 eV - 1566 keV parameters are taken from BNL 325 4th edition/1/, and some parameters are assumed to fit the measured data. cross sections calculated with these parameters are to be corrected by adding mf=3, mt=1, 2 and 102 data. calculated 2200-m/s cross sections and resonance integrals 2200-m/sec res. integ. ref. elastic 0.963 b - - capture 0.528 b 0.250 b /1/ total 1.499 b - - mf=3 Neutron cross sections Below 1566keV background data for mt=107 0.007 b, based on 2200-m/s data of ref./1/. Above 1566keV mt=1, 2, 4, 51-56, 91, 102 Total, elastic, inelastic and capture calculated with casthy code /2/, considering the competition with the threshold reaction channels. Optical potential parameters of C.Y.Fu/3/ are adjusted to reproduce the following experimental data: mt=1 total - mt=2 elastic G.A.Petitt et al./4/, A.Virdis/5/. mt=4 inelastic - The spherical optical potential parameters: V=38.0 Vso=5.37 (MeV) Ws=9.13 Wv =0.0 (MeV) r =rso=1.26 rs=1.39 (fm) a=aso =0.76 b =0.40(fm) mt=102 Capture data are normalized to the experimental data of A.Lindholm et al. at 3 - 6 MeV/6/. The discrete level scheme taken from ref./7/: no. energy(MeV) spin-parity (g.s.) 0.0 0+ 1 2.230 2+ 2 3.779 0+ 3 4.282 2+ 4 4.459 4+ 5 4.695 1+ 6 5.006 3- Continuum levels assumed above 5.4 MeV. The level density parameters of Asano et al./8/are used. ***** JENDL-3.2 **************************************** mt=1,4,51-56,91,251 Coupled-channel optical and statistical model calculation was performed by using the omp set given as follows: V = 58.83 - 0.5635En (MeV) Ws = 2.518 + 0.0302En (MeV) Vso= 4.199 (MeV) r = 1.306, a = 0.452 (fm) rs = 1.124, b = 0.690 (fm) rso= 1.010, aso= 0.750 (fm). the coupling scheme ground state 0.0 MeV (0+) 1 phonon state 2.230 MeV (2+), 5.006 MeV (3-) 2 phonon state 3.779 MeV (0+), 4.280 MeV (2+) 4.459 MeV (4+) coupling constants beta-2 = 0.30 beta-3 = 0.25 ********************************************************* mt=16(n,2n), 22(n,n'a), 28(n,n'p), 103(n,p), 107(n,a) Based on the statistical model calculations with gnash code/9/, without the precompound reaction correction. transmission coefficients for proton and alpha particles are calculated by using the omp of Becchetti-Geenlees /10/ and Huizenga-Igo/11/, respectively. Level density parameters are based on built-in values. mt=103 (n,p) cross section Adjusted to reproduce R. Ricamo data above 14 MeV /12/. mf=4 Angular distributions of secondary neutrons mt=2 Calculated with optical model (casthy). mt=51-56 Calculated with coupled-channel statistical model mt=16,22,28 Isotropic in the laboratory system. mt=91 Isotropic distributions in cm were converted to the distributions in lab. mf=5 Energy distributions of secondary neutrons mt=16,22,28,91,103,107 evaporation spectra, mf=12 Photon production multiplicities mt=16,22,28,103,107 Multiplicities were calculated by using the egnash code /13/. mt=102 Multiplicities were calculated by using the casthy code /2/. mt=51-56 Transition probability arrays were given. mf=14 Photon angular distributions mt=16,22,28,51-56,91,102,103,107 Isotropic mf=15 Continuous photon energy spectra mt=16,22,28,103,107 Multiplicities were calculated by using the egnash code /13/. mt=102 Multiplicities were calculated by using the casthy code /2/. References 1) Mughabghab,S.F. et al.: Neutron cross section, Vol.1 (1981). 2) Igarasi,S.: J. Nucl. Sci. Tech. 12, 67 (1975). 3) Fu,C.Y.: Atom. Data and Nucl. Data Tables. 17, 127 (1976). 4) Petitt,G.A. et al.: Nucl. Phys. 79, 231 (1960). 5) Virdis,A.: CEA-R-5144 (1981). 6) Lindholm,A. et al.: Nucl. Phys. A279, 445 (1977). 7) Leder,C.M. et al.: Table of Isotopes. 7th edit. 8) Asano et al.: private communication. 9) Young,P.G. and Arthur,E.D.: LA-6947 (1977). 10) Becchetti,Jr. and Greenlees,G.W.: Polarization phenomena in nuclear reactions, p.682 (1971). 11) Huizenga,Jr. and Igo,G.J.: Nucl. Phys. 29, 462 (1962). 12) Ricamo, R. : NC 8, 383 (1951). 13) Yamamuro, N.: JAERI-M 90-006 (1990).