21-Sc- 45 KHI EVAL-AUG88 T.WATANABE DIST-DEC21 20090828 ----JENDL-5 MATERIAL 2125 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-11 revised by O.Iwamoto (MF8/MT4,16,22,28,32,41,102-108,111,112) JENDL/AD-2017 adopted (MF9/MT102) JENDL/AD-2017 adopted (MF10/MT16) JENDL/AD-2017 based =========================================================== The data were taken from JENDL-3.3. =========================================================== =========================================================== JENDL-3.2 data were automatically transformed to JENDL-3.3. Interpolation of spectra: 22 (unit base interpolation) (3,251) deleted, T-matrix of (4,2) deleted, and others. =========================================================== HISTORY 88-08 JENDL-2 MODIFIED BY T.WATANABE (KAWASAKI HEAVY INDUSTRIES, LTD.) 93-09 JENDL-3.2. COMPILED BY T.NAKAGAWA (NDC/JAERI) ***** MODIFIED PARTS FOR JENDL-3.2 ******************** (2,151) PARAMETERS OF 3.295-KEV RESONANCE (3,2), (3,102) *********************************************************** MF=1 GENERAL INFORMATION MT=451 DESCRIPTIVE DATA AND DICTIONARY MF=2 MT=151 RESONANCE PARAMETERS : 1.0E-5 EV - 100 KEV RESOLVED RESONANCES FOR MLBW FORMULA: PARAMETERS WERE EVALUATED BASED ON EXPERIMENTAL DATA /1/,/2/,/3/ AND MODIFIED TO REPRODUCE EXPERIMENTAL TOTAL CROSS SECTIONS. NEGATIVE ENERGY LEVELS WERE ADDED TO REPRODUCE THE TOTAL AND CAPTURE CROSS SECTIONS/4/ AT THERMAL AND THE TOTAL CROSS SECTION /5/ AT 2 KEV. FOR JENDL-3.2, CAPTURE WIDTH OF 3.295-KEV RESONANCE WAS CHANGED TO 0.71 EV/4/. CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS 2200 M/SEC RES. INTEG. ELASTIC 22.48 B - CAPTURE 27.14 B 11.85 B TOTAL 49.62 B - MF=3 NEUTRON CROSS SECTIONS : ABOVE 100 KEV MT=1,2,4,51-74,91,102 TOTAL, ELASTIC, INELASTIC AND CAPTURE CALCULATED WITH OPTICAL AND STATISTICAL MODEL. DIRECT INELASTIC REACTION CROSS SECTIONS WERE EVALUATED WITH DWBA /6/ AND ADDED TO COMPOUND PROCESSES. STATISTICAL MODEL CALCULATION WITH CASTHY CODE /7/ WAS PERFORMED. MT=102 CAPTURE CROSS SECTION WAS NORMALIZED TO THE EXPERIMENTAL DATA OF VOIGNIER+/8/, 11.2 MB AT 500 KEV. DIRECT CAPTURE CROSS SECTION WAS CALCULATED FROM A SIMPLE FORMULA OF BENZI AND REFFO/9/ AND NORMALIZED TO 1.0 MB AT 14.0 MEV. THE SPHERICAL OPTICAL POTENTIAL PARAMETERS WERE EVALUATED TO REPRODUCE TOTAL EXPERIMENTAL CROSS SECTIONS /10,11,12/. V = 56.2 - 0.3244*EN MEV R0= 1.155 FM A0= 0.666 FM WS= 8.638-0.003093*EN MEV RS= 1.473 FM B = 0.262 FM VSO=5.254 MEV RSO=1.003 FM ASO=0.485 FM THE LEVEL SCHEME TAKEN FROM REF./13/: NO. ENERGY(MEV) SPIN-PARITY BETA G.S 0.0 7/2- 1 0.012396 3/2+ 2 0.37659 3/2- 0.108 3 0.543 5/2+ 4 0.72017 5/2- 0.0867 5 0.9392 1/2+ 0.0211 6 0.97461 7/2+ 7 1.0672 3/2- 0.0586 8 1.23723 11/2- 0.143 9 1.30342 3/2+ 10 1.40887 7/2- 11 1.43367 9/2+ 12 1.5564 3/2- 13 1.66231 9/2- 0.0843 14 1.8004 5/2+ CONTINUUM LEVELS ASSUMED ABOVE 1.9 MEV LEVEL DENSITY PARAMETERS WERE EVALUATED USING D0/4/, AND LEVEL DATA /13/. A T EX SIG**2(0) 21-SC-45 7.855 1.282 10.08 7.602 21-SC-46 7.231 1.268 7.328 7.867 MT=16 (N,2N) THE JENDL-2 DATA WERE MODIFIED BY USING EXPERIMENTAL DATA /14/. MT=103 (N,P) TAKEN FROM COMPILATION BY ALLEY AND LESSLER /15/ MT=107 (N,ALPHA) SAME AS MT=103, BUT SLIGHTLY MODIFIED TO REPRODUCE EXPERIMENTAL DATA/14/. MT=251 MU-BAR CALCULATED FROM THE DATA IN MF=4. MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS MT=2 CALCULATED WITH OPTICAL MODEL. MT=51-91 CALCULATED WITH HAUSER-FESHBACH FORMULA ADDED WITH DIRECT REACTION. MT=16 ISOTROPIC IN THE LABORATORY SYSTEM MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS CALCULATED WITH SINCROS /16/. REFERENCES 1) LIOU, H.I. ET AL.: NUCL. SCI. ENG. 67, 326 (1978). 2) KENNY, M.J. ET AL.: AUSTRALIAN J. PHYS. 30, 605 (1977). 3) ALLEN, B.J. ET AL.: NUCL. SCI. ENG. 82, 230 (1982). 4) MUGHABGHAB, S.F., ET AL: 'NEUTRON CROSS SECTIONS VOL.1 PART A' ACADEMIC PRESS (1981) 5) FUJITA, Y: J. NUCL. SCI. TECHNOL. 20, 191 (1983). 6) KUNZ, P.D.: UNPUBLISHED (1974). 7) IGARASI, S. AND FUKAHORI, T.: JAERI 1321 (1991). 8) VOIGNIER, J, ET AL.: NUCL. SCI. ENG. )3, 43 (1986). DATA WERE TAKEN FROM EXFOR 9) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969). 10) POENITZ, W.P. AND WHALEN, J.F.: ANL/NDM-80 (1983). 11) BARNARD, E. ET AL.: Z. PHYS. 245, 36 (1971). 12) FOSTER, JR. D.G. AND GLASGOW D.W.: PHYS. REV. C3, 576 (1971). 13) BURROWS, T.W.: NUCLEAR DATA SHEETS 40, 216 (1983). 14) IKEDA, Y., ET AL.: JAERI 1312 (1988). 15) ALLEY, W.E. AND LESSLER, R.M: NUCLEAR DATA TABLES A11,648 (1973). 16) YAMAMURO, N.: JAERI-M 88-140 (1988).