3-Li- 6 JAERI EVAL-MAR85 S.CHIBA AND K.SHIBATA JAERI-M 88-164 DIST-DEC21 20090827 ----JENDL-5 MATERIAL 325 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-11 revised by O.Iwamoto (MF8/MT16,102,103,105) JENDL/AD-2017 adopted (MF8/MT4) added =========================================================== 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 83-12 NEWLY EVALUATED BY K.SHIBATA 84-07 DATA OF MF=4 (MT=16,91) AND MF=5 (MT=16,91) WERE REVISED. COMMENT WAS ALSO MODIFIED. 85-03 MODIFIED BY S. CHIBA DATA OF MF=3 (MT=59,63) AND MF=4 (MT=59,63) WERE ADDED. DATA OF MF=3 (MT=16), MF=4 (MT=2,16,53), MF=5 (MT=16) WERE REVISED. PSEUDO-LEVEL REPRESENTATION WAS ADOPTED FOR THE (N,N')ALPHA-D CONTINUUM (MT=51,52,54-56,58,60-62,64-86). 93-12 MODIFIED BY S. CHIBA FOR JENDL-3.2 DATA OF MF=3 (MT=2,3,4,54-56,58,82) AND MF=4 (MT=16,51,52, 54-58,60-86) WERE ADJUSTED MAMUALLY TO REPRODUCE THE DDX DATA AT 14 AND 18 MEV /1,2,3/. **** MODIFIED PARTS FOR JENDL-3.2 ****************************** (3,2),(3,3),(3,4),(3,54-56),(3,58-82) ABOVE 10 MEV (4,16),(4,51-52),(4,54-58),(4,60-86) ****************************************************************** MF=1 GENERAL INFORMATION MT=451 DESCRIPTIVE DATA MF=2 RESONANCE PARAMETERS MT=151 SCATTERING RADIUS ONLY. MF=3 CROSS SECTIONS CALCULATED 2200M/S CROSS SECTIONS AND RES. INTEGRALS 2200M/S (B) RES. INTEG. (B) TOTAL 94.11 - ELASTIC 0.735 - CAPTURE 0.039 0.017 (N,T) 94.03 - MT=1 SIG-T BELOW 1 MEV BASED ON THE R-MATRIX CALCULATION. SIG-CAP WAS ADDED TO THE CALCULATED CROSS SECTION. ABOVE 1 MEV, BASED ON THE EXPERIMENTAL DATA /4,5,6/. MT=2 SIG-EL BELOW 1 MEV, BASED ON THE R-MATRIX CALCULATION. ABOVE 1 MEV, THE CROSS SECTION WAS OBTAINED BY SUBTRACTING THE REACTION CROSS SECTION FROM THE TOTAL CROSS SECTION. MT=3 NON-ELASTIC SUM OF MT=4, 16, 102, 103 AND 107. MT=4 TOTAL INELASTIC SUM OF MT=51, 52, 53, 54 AND 91. MT=16 (N,2N)LI5 BASED ON THE EXPERIMENTAL DATA /7,8,9/. MT=53 SIG-IN 2.185 MEV BASED ON THE EXPERIMENTAL DATA /1,2,3,6,10,11,12,13/. MT=57 SIG-IN 3.562 MEV BASED ON THE EXPERIMENTAL DATA /1,2,3,6,14/ MT=59 SIG-IN 4.31 MEV BASED ON A COUPLED-CHANNEL CALCULATION. THE SYMMETRIC ROTATIONAL MODEL WAS ASSUMED. THE COUPLING SCHEME WAS 1+(G.S.) - 3+(2.185) - 2+(4.31) - 1+(5.7). THE POTENTIAL PARAMETERS WERE; V = 45.0766 MEV, R = 1.1875 FM, A = 0.57335 FM WS = 0.4432*EL-1.1631 MEV, RI= 1.6113 FM, AI = 0.26735 FM VSO= 5.5 MEV, RSO=1.15 FM, ASO= 0.5 FM BETA(2)=1.1395, WHERE EL MEANS THE INCIDENT NEUTRON ENERGY IN THE LAB. SYSTEM (MEV). ABOVE 10 MEV, BASED ON EXPERIMENTAL DATA /1,2,3/. MT=63 SIG-IN 5.7 MEV BASED ON THE CC CALCULATION NORMALIZED TO THE EXPERIMENTAL DATA /9/. ABOVE 10 MEV, BASED ON EXPERIMENTAL DATA /1,2,3/. MT=51,52,54-56,58,60-62,64-86 (N,N')ALPHA-D CONTINUUM REPRESENTED BY PSEUDO-LEVELS, BINNED IN 0.5 MEV INTERVALS. THE (N,N')ALPHA-D CROSS SECTION WAS BASED ON THE MEASURE- MENT OF ROSEN AND STEWART /15/. THE CONTRIBUTION FROM MT=53, 59 AND 63 WAS SUBTRACTED SO THAT SIG-T MIGHT BE EQUAL TO THE SUM OF PARTIAL CROSS SECTIONS. THE CROSS SECTION FOR EACH LEVEL WAS CALCULATED BY THE 3-BODY PHASE- SPACE DISTRIBUTION WITH A CORRECTION OF THE COULOMB INTERACTION IN THE FINAL STATE, ASSUMING ISOTROPIC CENTER- OF-MASS DISTRIBUTIONS. ADJUSTED TO REPRODUCE THE DDX DATA AT 14 AND 18 MEV /1,2,3/ MT=102 CAPTURE BELOW 100 KEV, 1/V CURVE NORMALIZED TO THE THERMAL DATA OF JURNEY /16/. ABOVE 100 KEV, THE INVERSE REACTION DATA OF FERDINANDE ET AL./17/ WERE ADDED. MT=103 (N,P) BASED ON THE EXPERIMENTAL DATA /18,19/. MT=105 (N,T)ALPHA BELOW 1 MEV, R-MATRIX CALCULATION. ABOVE 1 MEV, BASED ON THE EXPERIMENTAL DATA /20,21/. MT=251 MU-BAR CALCULATED FROM THE DATA IN FILE4. MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS MT=2 BELOW 500 KEV, R-MATRIX CALCULATION. BETWEEN 500 KEV AND 14 MEV, BASED ON THE EXPERIMENTAL DATA /4,10,22/. ABOVE 15 MEV, BASED ON THE CC CALCULATION. MT=16 BASED ON THE EXPERIMENTAL DATA /1,2,3,9/. ANGULAR DISTRIBUTIONS ARE GIVEN IN THE LABORATORY SYSTEM. MT=53 BELOW 4.8 MEV, ASSUMED TO BE ISOTROPIC IN CM. BETWEEN 4.8 AND 14 MEV, BASED ON THE EXPERIMENTAL DATA /10,23/. ABOVE 15 MEV, THE CC CALCULATION. MT=57 BASED ON EXPERIMENTAL DATA /1,2,3/. MT=59 BASED ON THE CC CALCULATION. MT=63 BASED ON EXPERIMENTAL DATA /1,2,3/. MT=51,52,54-56,58,60-62,64-86 ADJUSTED TO REPRODUCE THE DATA /1,2,3/. MF=5 ENERGY DISTRIBUTION OF SECONDARY NEUTRONS MT=16 THE EVAPORATION MODEL WAS ASSUMED. THE EVAPORATION TEMPERATURE OF REF./9/ WAS ADOPTED. IT WAS EXTRAPOLATED AS T = 0.176497*SQRT(EL) MEV, WHERE EL MEANS THE INCIDENT NEUTRON ENERGY IN THE LAB. SYSTEM (MEV). MF=12 PHOTON-PRODUCTION MULTIPLICITIES MT=57 M=1.0 MT=102 BASED ON THE THERMAL MEASUREMENT OF JURNEY /15/. MF=14 PHOTON ANGULAR DISTRIBUTIONS MT=57 ISOTROPIC MT=102 ASSUMED TO BE ISOTROPIC. REFERENCES 1) TAKAHASII A. ET AL., TO BE PUBLISHED. 2) MATSUYAMA S. ET AL., TO BE PUBLISHED. 3) CHIBA S. ET AL., PPROC OF MITO CONF, P.253(1988). 4) KNITTER H.-H. ET AL.: EUR-5726E (1977). 5) LAMAZE G.P. ET AL.: BULL. AM. PHYS. SOC. 24 (1979) 862. 6) GUENTHER P. ET AL.: ANL/NDM-52 (1980). 7) MATHER D.S. AND PAIN L.F.: AWRE-O-47/69 (1969). 8) ASHBY V.J. ET AL.: PHYS. REV. 129 (1963) 1771. 9) CHIBA S. ET AL.: J. NUCL. SCI. TECHNOL. 22 (1985) 771. 10) HOGUE H.H. ET AL.: NUCL. SCI. ENG. 69 (1979) 22. 11) LISOWSKI P.W. ET AL.: LA-8342 (1980). 12) FOERTSCH H. ET AL.: ZFK-443 (1981), P.13. 13) DRAKE D.D.: DOE/NDC-24/U (1981), P.72. 14) BESOTOSNYJ ET AL.: YK-19 (1975), P.77. 15) ROSEN L. AND STEWART L.: PHYS. REV. 126 (1962) 1150. 16) JURNEY E.T.: USNDC-9 (1973), P.109. 17) FERDINANDE H. 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