3-Li- 7 JAERI EVAL-DEC84 S.CHIBA AND K.SHIBATA JAERI-M 88-164 DIST-DEC21 20090827 ----JENDL-5 MATERIAL 328 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-11 revised by O.Iwamoto (MF8/MT16,22,102,104) 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. 84-12 MODIFIED BY S. CHIBA DATA OF MT=62 AND 64(MF=3,4) WERE ADDED. DATA OF MF=4 (MT=2,51,57,16) AND MF=5 (MT=16,91) WERE MODIFIED. PSEUDO-LEVEL REPRESENTATION WAS ADOPTED FOR THE (N,N')ALPHA-T CONTINUUM (MT=52-56,58-61,63,65-84). COMMENT WAS ALSO MODIFIED. 87-02 LI7(N,NT) CROSS SECTION WAS MODIFIED. 88-02 LI7(N,N2) CROSS SECTION AND ANG. DIST. WERE MODIFIED. LI7(N,N0) WAS ALSO MODIFIED SO AS TO GIVE THE TOTAL CROSS SECTION WHICH IS EQUAL TO JENDL-3PR1. THE LI7(N,N1) ANG. DIST. WAS ALSO MODIFIED. LI7(N,NT) CROSS SECTION WAS FIXED TO 87-02 VERSION BY MODIFYING THE PSEUDO-LEVEL CROSS SECTIONS. COMMENT WAS ALSO MODIFIED. 92-11 JENDL-3.2 COMPILED BY T.NAKAGAWA ***** MODIFIED PARTS FOR JENDL-3.2 ******************** (4,2) NUMBER OF ELEMENTS OF TRANSFORMATION MATRIX *********************************************************** 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 2200 M/S (B) RES. INTEG. (B) TOTAL 1.015 - ELASTIC 0.97 - CAPTURE 0.045 0.020 MT=1 SIG-T BELOW 100 KEV, SIG-T = 0.97 + SIG-CAP (BARNS). ABOVE 100 KEV, BASED ON THE EXPERIMENTAL DATA /1/-/4/. MT=2 SIG-EL BELOW 100 KEV, SIG-EL = 0.97 (BARNS). ABOVE 100 KEV, SIG-EL = SIG-T - SIG-REACT. MT=3 NON-ELASTIC SUM OF MT=4, 16, 102 AND 104. MT=4 TOTAL INELASTIC SUM OF MT=51 TO 84. MT=16 (N,2N) BASED ON THE EXPERIMENTAL DATA /5/,/6/. MT=51 SIG-IN 0.478 MEV BASED ON THE (N,N'GAMMA) DATA OF MORGAN /7/. MT=57 SIG-IN 4.63 MEV BASED ON THE EXPERIMENTAL DATA /8/-/10/. MT=62 SIG-IN 6.68 MEV BASED ON A COUPLED-CHANNEL CALCULATION NORMALIZED TO THE EXPERIMENTAL DATA /13,14/. THE SYMMETRIC ROTATIONAL MODEL WAS ASSUMED. THE COUPLING SCHEME WAS 3/2-(G.S.) - 1/2-(0.478) - 7/2-(4.63) - 5/2-(6.68). THE POTENTIAL PARAMETERS WERE AS FOLLOWS; V= 49.6 - 0.362*EL MEV, R= 1.28 FM, A= 0.620 FM WS= -13.2 + 1.88*EL MEV, RI= 1.34 FM, AI= 0.104 FM VSO= 5.500 MEV, RSO=1.150 FM, ASO=0.50 FM BETA(2)= 0.952, WHERE EL MEANS LABORATORY INCIDENT ENERGY IN MEV. MT=64 SIG-IN 7.467 MEV ASSUMED TO HAVE THE SAME EXCITATION FUNCTION AS MT=53, NORMALIZED TO THE EXPERIMENTAL DATA /13,14/. MT=52-56,58-61,63,65-84, (N,N')ALPHA-T CONTINUUM REPRESENTED BY PSEUDO-LEVELS, BINNED IN 0.5 MEV INTERVALS. THE CROSS SECTION WAS OBTAINED BY SUBTRACTING THE CONTRIBUTION OF MT=57,62 AND 64 FROM THE (N,N')ALPHA-T CROSS SECTION (MT=205). 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. MT=102 CAPTURE 1/V NORMALIZED TO THE THERMAL MEASUREMENT /15/. MT=104 (N,D) THE (N,D) CROSS SECTION WAS CALCULATED WITH DWBA. NORMALIZATION WAS TAKEN SO THAT THE CALCULATED CROSS SECTION MIGHT BE CONSISTENT WITH THE ACTIVATION DATA /16/. MT=205 (N,N')ALPHA-T BASED ON THE EXPERIMENTAL DATA /17/-/22/. MT=251 MU-BAR CALCULATED FROM THE DATA IN FILE4. MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS MT=2 BELOW 4 MEV, AN R-MATRIX CALCULATION WITH THE PARAMETERS OF KNOX AND LANE/23/. BETWEEN 4 MEV AND 14 MEV, BASED ON THE EXPERIMENTAL DATA /8/,/24/. ABOVE 15 MEV, THE COUPLED-CHANNEL CALCULATION. MT=16 BASED ON THE EXPERIMENTAL DATA /13/ AT 14.2 MEV. ANGULAR DISTRIBUTIONS ARE GIVEN IN THE LABORATORY SYSTEM. MT=51 BELOW 4 MEV, THE R-MATRIX CALCULATION. 4 TO 10 MEV, EVALUATION OF LISKIEN/25/ WAS ADOPTED. ABOVE 10 MEV, THE COUPLED-CHANNEL CALCULATION. MT=57 BELOW 8 MEV, THE R-MATRIX CALCULATION. BETWEEN 8 MEV AND 14 MEV, BASED ON THE EXPERIMENTAL DATA /10/-/12/. ABOVE 15 MEV, THE COUPLED-CHANNEL CALCULATION. MT=62 AT THE THRESHOLD, AN ISOTROPIC DISTRIBUTION WAS ASSUMED. ABOVE 10 MEV, THE COUPLED-CHANNEL CALCULATION. MT=64 ISOTROPIC DISTRIBUTIONS WERE ASSUMED IN THE CENTER-OF-MASS SYSTEM. MT=52-56,58-61,63,65-84 EXPERIMENTAL DATA/13/ WERE ADOPTED. MF=5 ENERGY DISTRIBUTION OF SECONDARY NEUTRONS MT=16 THE EVAPORATION MODEL WAS ASSUMED, WITH THE TEMPERATURE DEDUCED EXPERIMENTALLY/13/ AT 14.2 MEV. THE TEMPERATURE WAS EXTRAPOLATED AS T = 0.229*SQRT(EL) MEV, WHERE EL MEANS LABORATORY INCIDENT ENERGY IN MEV. MF=12 PHOTON-PRODUCTION MULTIPLICITIES MT=51 M=1.0 MT=102 MULTIPLICITIES WERE OBTAINED FROM REF./26/. MF=14 PHOTON ANGULAR DISTRIBUTIONS MT=51 ISOTROPIC MT=102 ASSUMED TO BE ISOTROPIC. REFERENCES 1) MEADOWS J.W. AND WHALEN J.F.: NUCL. SCI. ENG. 41 (1970) 351. 2) FOSTER, JR. D.G. AND GLASGOW D.W.: PHYS. REV. C3 (1971) 576. 3) GOULDING C.A. ET AL.: USNDC-3 (1972), P.161. 4) LAMAZE G.P. ET AL.: BULL. AM. PHYS. SOC. 24 (1979) 862. 5) MATHER D.S. AND PAIN L.F.: AWRE-O-47/69 (1969). 6) ASHBY V.J. ET AL.: PHYS. REV. 129 (1963) 1771. 7) MORGAN G.L.: ORNL/TM-6247 (1978). 8) HOGUE H.H. ET AL.: NUCL. SCI. ENG. 69 (1979) 22. 9) BABA M. ET AL.: PROC. INT. CONF. 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