16-S - 33 FUJI E.C. EVAL-MAY87 H.NAKAMURA DIST-MAY10 20090828 ----JENDL-4.0 MATERIAL 1628 -----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 New optical model calculation was performed by T. Watanabe (khi). Data were compiled by K. Shibata (jaeri). ***** modified parts for JENDL-3.2 ****************** (3,1),(3,4),(3,51-57),(3,91),(3,251),(4,2),(4,51-57) optical and statistical model 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 - 260 keV Parameters are taken from BNL325 4th edition/1/, and C.Wagemans and H.Weigmann/2/. Cross sections calculated with these parameters are to be corrected 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 2.84 b - /1/ capture 0.35 b 0.164 b /1/ total 3.36 b - - mf=3 Neutron cross sections Below 260 keV Background cross sections are given for mt=1: mt=1 0.171b : 0.002(n,p) + 0.169(n,a) b mt=103 (n,p) 0.0016 b, based on 2200-m/s data /1/. mt=107 (n,a) 0.169 b, same to the above. Above 260 keV mt=1,2,4,51-57,91,102 Total, elastic, inelastic and capture cross sections calculated with casthy code /3/, considering the competition with the threshold reaction channels. Optical potential parameters of C.Y.Fu/4/ are adjusted to reproduce the following experimental data: mt=1 total - mt=2 elastic cross sections of s-32. 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 0.5 mb at 260 keV based on s-32 capture cross sections. The discrete level scheme taken from ref./5/: no. energy(MeV) spin-parity (g.s.) 0.0 3/2 + 1 0.8404 1/2 + 2 1.966 5/2 + 3 2.313 3/2 + 4 2.866 5/2 + 5 2.934 7/2 - 6 2.969 7/2 + 7 3.220 3/2 - Continuum levels are assumed above 3.6MeV. The level density parameters of Asano et al./6/ are used. ***** JENDL-3.2 **************************************** mt=1,4,51-57,91,251 Optical and statistical model calculation was performed by using the omp set given as follows: V = 58.83 - 0.5635En (MeV) Ws = 3.609 + 0.1819En (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). ********************************************************* 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 /7/, without the precompound reaction correction. Transmission coefficients for proton and alpha particles are calculated by using the omp of becchetti-geenlees/8/ and huizenga-igo/9/, respectively. Level density parameters are based on built-in values. mf=4 Angular distributions of secondary neutrons mt=2 Calculated with optical model (casthy). mt=51-57 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 /10/. mt=102 Multiplicities were calculated by using the casthy code /3/. mt=51-57 Transition probability arrays were given. mf=14 Photon angular distributions mt=16,22,28,51-57,91,102,103,107 Isotropic mf=15 Continuous photon energy spectra mt=16,22,28,103,107 Multiplicities were calculated by using the egnash code /10/. mt=102 Multiplicities were calculated by using the casthy code /3/. References 1) Mughabghab, S.F. et al.: Neutron cross section, Vol.1 (1981). 2) Wagemans, C. and Weigman, H.: Grenoble-conf., 462 (1981). 3) Igarasi, S.: J. Nucl. Sci. Tech., 12, 67 (1975). 4) Fu, C.Y.: Atom.Data and Nucl. Data Tables, 17, 127 (1976). 5) Ledrer, C.M. et al.: Table of isotopes. 7th edit. 6) Asano et al.: private communication. 7) Young, P.G. and Arthur, E.D.: LA-6947 (1977). 8) Becchetti, Jr. and Greenlees, G.W.: Polarization phenomena in nuclear reactions, p.682 (1971). 9) Huizenga, Jr. and Igo, G.J.: Nucl. Phys., 29, 462 (1962). 10) Yamamuro, N.: JAERI-M 90-006 (1990).