3-Li- 7
3-Li- 7 JAERI EVAL-DEC84 S.CHIBA AND K.SHIBATA
JAERI-M 88-164 DIST-MAY10 20090827
----JENDL-4.0 MATERIAL 328
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
===========================================================
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. NUCLEAR CROSS SECTIONS
FOR TECHNOLOGY, KNOXVILLE, 1979, (1980) P.143.
10) LISOWSKI P.W. ET AL.: LA-8342 (1980).
11) SCHMIDT D. ET AL.: NUCL. SCI. ENG. 96 (1987) 159.
12) CHIBA S. ET AL.: J. NUCL. SCI. TECHNOL. 25 (1988) 210.
13) CHIBA S. ET AL.: J. NUCL. SCI. TECHNOL. 22 (1985) 771.
14) TAKAHASHI A. ET AL.: PRIVATE COMMUNICATION.
15) JURNEY E.T.: USNDC-9 (1973), P.109.
16) BATTAT M.E. AND RIBE F.L.: PHYS. REV. 89 (1953) 80.
17) SMITH D.L. ET AL.: NUCL. SCI. ENG. 78 (1981) 359.
18) LISKIEN H. ET AL.: PROC. INT. CONF. NUCLEAR DATA FOR
SCIENCE AND TECHNOLOGY, ANTWERP 1982, (1983) P.349.
19) SMITH D.L. ET AL.: ANL/NDM-87 (1984).
20) TAKAHASHI A. ET AL.: PROC. 13TH SYMP. FUSION TECH., VARESE,
ITALY (1984).
21) GOLDBERG E. ET AL.: NUCL. SCI. ENG. 91, 173 (1985).
22) MAEKAWA H. ET AL.: JAERI-M 86-125, P.130 (1986).
23) KNOX H.D. AND LANE R.O.: NUCL. PHYS. A359 (1981) 131.
24) KNOX H.D. ET AL.: NUCL. SCI. ENG. 69 (1979) 223.
25) LISKIEN H.: PRIVATE COMMUNICATION.
26) AJZENBERG-SELOVE F. AND LAURITSEN T.: NUCL. PHYS. A227(1974)1.