3-Li- 6
3-LI- 6 JAERI EVAL-MAR85 S.CHIBA AND K.SHIBATA
JAERI-M 88-164 DIST-SEP89 REV2-DEC93
----JENDL-3.2 MATERIAL 325
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
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. ET AL.: CAN. J. PHYS. 55 (1977) 428.
18) PRESSER G. ET AL.: NUCL. PHYS. A131 (1969) 679.
19) MERCHEZ F. ET AL.: NUCL. PHYS. A182 (1972) 428.
20) BARTLE C.M.: NUCL. PHYS. A330 (1979) 1.
21) BARTLE C.M. ET AL.: NUCL. PHYS. A397 (1983) 21.
22) KNOX H.D. ET AL.: NUCL. SCI. ENG. 69 (1979) 223.
23) HOPKINS J.C. ET AL.: NUCL. PHYS. A107 (1968) 139.