19-K - 39 FUJI E.C. EVAL-MAY87 H.NAKAMURA DIST-JUL13 20130521 ----JENDL-4.0u1 MATERIAL 1925 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT =========================================================== The data were taken from JENDL-3.3. =========================================================== HISTORY 87-05 Newly evaluated by H.Nakamura (fuji electric co. ltd.) 94-02 JENDL-3.2 Total cross section was calculated by T. Watanabe (khi). Inelastic scattering cross sections were calculated by K.Shibata (jaeri). Data were compiled by K.Shibata. ***** modified parts for JENDL-3.2 **************************** (3,1),(3,4),(3,51-91),(3,251),(4,2),(4,51-54) new optical and statistical model cal. (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. **************************************************************** 13-05 Modified by K.Shibata for JENDL-4.0u1 (5,16) Spectrum at 4.25 MeV was revised to avoid negative Kerma factors. (12,91) Multiplicities were modified near threshold to keep energy balance. 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 - 200 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 integlals 2200-m/sec res.integ. ref. elastic 2.06 b - - capture 2.10 b 1.1 b /1/ total 4.16 b - - mf=3 Neutron cross sections Below 200 kev Background data for mt=1 : (mt=107)-cross sections. mt=107 (n,a)=0.04 b (10**-5 eV), 0.0043 b (2200m/s)/1/, int=5. Above 200 keV mt=1,2,4,51-54,91,102 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 used. The spherical optical potential parameters: V = 46.72 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 4.2 mb at 200 keV. The discrete level scheme taken from ref./4/: no. energy(MeV) spin-parity (g.s) 0.0 3/2 + 1 2.523 1/2 + 2 2.814 7/2 - 3 3.019 3/2 - 4 3.598 9/2 - Continuum levels assumed above 3.8 MeV. The level density parameters of Asano et al./5/ are used. ***** JENDL-3.2 ******************************************** The total and inelastic scattering cross sections were cal- culated by using the omp set determined by T. Watanabe. V = 54.36 - 0.325En (MeV) Ws= 2.258 + 0.1698En (MeV) Vso=3.341 (MeV) r =1.20 ,a =0.658 (fm) rs =1.32 ,b =0.602 (fm) rso=1.10 ,aso=0.406 (fm) The cross sections of mt=16,22,28,103,107 in JENDL-3.1 were considered as the competing process for the statistical model calculation. ************************************************************ 200 keV - 1.0 MeV mt=107 (n,a)-cross section = 2.6*10**-5 b (constant): assumed from the calculated value at 1.0 MeV. Above 1.0 MeV mt=16,22,28,103,107 (n,2n), (n,na), (n,np), (n,p), (n,a) Based on the statistical model calculations with gnash code/6/, without the precompound reaction correction. transmission coefficients for proton and alpha particle are calculated by using the omp of Becchetti-Greenlees /7/ and Huizenga-Igo/8/, respectively. Level density parameters are based on built-in values. At the energy range of 4 - 20 MeV, (n,p) cross section was based on the experimental data/9-11/. mf=4 Angular distributions of secondary neutrons mt=2 Calculated with optical model (casthy). mt=51-54 Calculated with Hauser-Feshbach formula (casthy) 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 /12/. mt=102 Multiplicities were calculated by using the casthy code /2/. mt=51-54 Transition probability arrays were given. mf=14 Photon angular distributions mt=16,22,28,51-54,91,102,103,107 Isotropic mf=15 Continuous photon energy spectra mt=16,22,28,103,107 Multiplicities were calculated by using the egnash code /12/. 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) Lederer, C.M. et al.: Table of isotopes. 7th edit. 5) Asano et al.: private communication. 6) Young, P.G. and Arthur, E.D.: LA-6947 (1977). 7) Becchetti, Jr. and Greenlees, G.W.: Polarization phenomena in nuclear reactions, p.682 (1971). 8) Huizenga, Jr. and Igo, G.J.: Nucl. Phys., 29, 462 (1962). 9) Bass, R. et al.: Nucl. Phys., 56, 569 (1964). 10) Bormann, M. et al.: Zeitschrift f. Naturforschung, Section A, 15, 200 (1960). 11) Aleksandrov,D.V. et al.: Atomnaya Energiya, 39(2), 137 (1975). 12) Yamamuro, N.: JAERI-M 90-006 (1990).