13-Al- 27
13-AL- 27 TIT,JAERI EVAL-MAR88 Y.HARIMA,H.KITAZAWA,T.FUKAHORI
88MITO, 473 DIST-DEC89 REV2-DEC93
----JENDL-3.2 MATERIAL 1325
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
88-03 EVALUATION WAS PERFORMED FOR JENDL-3 BY HARIMA, KITAZAWA
(TOKYO INSTITUTE OF TECH.) AND FUKAHORI (JAERI). DETAILS
ARE GIVEN IN REF./1/.
88-03 COMPILED BY FUKAHORI.
93-12 JENDL-3.2.
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(3,2)
(3,66-91) TAKEN FROM JENDL FUSION FILE*
(3,4), (3,51-70) CROSS-SECTION CURVES WERE SMOOTHED.
(4,16-28), (4,91) TAKEN FROM JENDL FUSION FILE
(5,16-91) TAKEN FROM JENDL FUSION FILE
(12,51-70), (12,102)
***********************************************************
-------------------------------------------------------------
JENDL FUSION FILE /2/ (AS IS SEP. 1993)
EVALUATED BY B.YU (CIAE) AND S.CHIBA (NDC/JAERI)
COMPILED BY B.YU.
CROSS SECTIONS WERE MAINLY TAKEN FROM JENDL-3.1, EXCEPT
FOR THE (N,N') (MT=66 TO 70) AND (N,N') CONTINUUM (MT=91)
REACTIONS WHICH WERE TAKEN FROM THE CALCULATION WITH
SINCROS-II/3/. ANGULAR DISTRIBUTIONS OF THESE LEVELS
WERE TAKEN TO BE EQUAL TO THAT OF MT=66 IN JENDL-3.
EDXS FOR MT=16, 22, 28 AND 91 WERE REPLACED BY THE
SINCROS-II CALCULATION. MF=6 WERE CREATED BY F15TOB
PROGRAM. KUMABE'S SYSTEMATICS/4/ WAS USED. THE PRE-
COMPOUND/COMPOUND RATIO WAS TAKEN FROM THE SINCROS-II
CALCULATION.
OPTICAL-MODEL, LEVEL DENSITY AND OTHER PARAMETERS USED
IN THE SINCROS-II CALCULATION ARE DESCRIBED IN REF./3/.
LEVEL SCHEMES WERE DETERMINED ON THE BASIS OF ENSDF/5/.
-------------------------------------------------------------
MF=1 GENERAL INFORMATION
MT=451 DESCRIPTIVE DATA AND DICTIONARY
MF=2 RESONANCE PARAMETERS:
MT=151
RESOLVED RESONANCES : 1.0E-5 EV - 0.21 MEV
THE RESONANCE PARAMETERS WERE SEARCHED, USING MLBW FORMULA/6/.
AN INITIAL GUESS OF THE PARAMETERS SEARCH WAS TAKEN FROM REF.
/7/.
CALCULATED 2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200-M/SEC RES. INTEG.
ELASTIC 1.414 B -
CAPTURE 0.231 B 0.123 B
TOTAL 1.645 B -
MF=3 NEUTRON CROSS SECTIONS
MT=1 TOTAL CROSS SECTION
BETWEEN 0.21 AND 20 MEV, THE CROSS SECTIONS WERE OBTAINED BY
AN EYE-GUIDE SO AS TO FOLLOW THE EXPERIMENTAL DATA.
MT=2 ELASTIC SCATTERING CROSS SECTIONS
OBTAINED BY SUBTRACTING PARTIAL CROSS SECTIONS FROM THE
TOTAL CROSS SECTIONS.
MT=4,51-70,91 INELASTIC SCATTERING CROSS SECTIONS
FOR JENDL-3.1, CROSS SECTIONS UP TO 17-TH LEVEL WERE CALCULATED
WITH THE STATISTICAL-MODEL CODE CASTHY /8/ AND THE COUPLED-
CHANNEL MODEL CODE ECIS /9/ OR JUPITOR-1 /10/, TAKING ACCOUNT
OF COMPETITIVE PROCESSES FOR NEUTRON, PROTON, ALPHA-PARTICLE
AND GAMMA-RAY EMISSION/1/. THE FOLLOWING LEVELS/11/ WERE
TAKEN INTO ACCOUNT.
NO. ENERGY(MEV) SPIN-PARITY
G.S. 0.0 5/2 +
1. 0.8438 1/2 +
2. 1.0145 3/2 +
3. 2.2100 7/2 +
4. 2.7340 5/2 +
5. 2.9814 3/2 +
6. 3.0040 9/2 +
7. 3.6780 1/2 +
8. 3.9560 5/2 +
9. 4.0540 3/2 -
10. 4.4090 5/2 +
11. 4.5103 11/2 +
12. 4.5800 7/2 +
13. 4.8120 5/2 +
14. 5.1550 3/2 -
15. 5.2460 5/2 +
16. 5.4199 5/2 +
17. 5.4330 9/2 +
CONTINUUM LEVELS WERE ASSUMED ABOVE 5.6 MEV. LEVEL DENSITY WAS
CALCULATED, USING THE GILBERT-CAMERON FORMULA. THE LEVEL-
DENSITY PARAMETERS WERE OBTAINED FROM A CUMULATIVE PLOT OF
OBSERVED LEVELS/1/.
FOR JENDL-3.2, CROSS SECTIONS FOR MT'S FROM 66 TO 70 AND CONTI-
NUUM INELASTIC WERE REPLACED WITH JENDL FUSION FILE. THESE MT'S
CORRESPOND TO THE FOLLOWING LEVELS.
16. 5.4199 5/2 +
17. 5.4328 5/2 +
18. 5.4384 5/2 +
19. 5.4998 7/2 +
20. 5.5507 3/2 +
ABOVE 5.6 MEV, CROSS SECTIONS WERE SUMMED UP AS THE CONTINUUM
INELASTIC (MT=91).
SEVERAL ENERGY POINTS WERE ADDED TO MT= 4, 51-70 IN ORDER TO
SMOOTH THEIR CROSS SECTION CURVES.
MT=16 (N,2N) CROSS SECTIONS
CALCULATED BY THE STATISTICAL MODEL WITH THE GNASH CODE/1,12/.
MT=22 (N,NA) CROSS SECTIONS
CALCULATED BY THE STATISTICAL MODEL WITH THE GNASH CODE/1,12/.
OPTICAL POTENTIAL FOR ALPHA-PARTICLES WAS DETERMINED, USING
THE DISPERSION THEORY /13/.
MT=28 (N,NP) CROSS SECTIONS
CALCULATED BY THE STATISTICAL MODEL WITH THE GNASH CODE/1,12/.
MT=102 CAPTURE
CALCULATED WITH THE STATISTICAL-MODEL CODE CASTHY/8/ AND THE
DIRECT-SEMIDIRECT-MODEL CODE HIKARI/14/. THE STATISTICAL-
MODEL CALCULATIONS WERE NORMALIZED TO 0.6 MB AT 0.6 MEV.
MT=103 (N,P) CROSS SECTIONS
CALCULATED BY THE STATISTICAL MODEL WITH THE GNASH CODE/1,12/.
MT=107 (N,A) CROSS SECTIONS
OBTAINED BY AN EYE-GUIDE TO FOLLOW OBSERVED VALUES /15/.
MT=111 (N,2P) CROSS SECTIONS
CALCULATED BY THE STATISTICAL MODEL WITH THE GNASH CODE/1,12/.
MT=251 MU-BAR
CALCULATED WITH STATISTICAL-MODEL CODE CASTHY /1,8/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2
CALCULATED WITH THE STATISTICAL-MODEL CODE CASTHY /1,8/.
MT=16,22,28
TAKEN FROM JENDL FUSION FILE.
MT=51-66
INCOHERENT SUM OF THE STATISTICAL MODEL AND COUPLED-CHANNEL
MODEL CALCULATIONS/1/. CALCULATED WITH CASTHY AND ECIS OR
JUPITOR-1.
MT=67-70
ASSUMED TO BE THE SAME AS MT=66.
MT=91
TAKEN FROM JENDL FUSION FILE.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,22,28,91
TAKEN FROM JENDL FUSION FILE.
MF=12 GAMMA-RAY MULTIPLICITIES (BELOW 5.80993 MEV)
MT=51-70
MULTIPLICITIES WERE CALCULATED FROM TRANSITION PROBABILITIES.
MT=102
CALCULATED FROM ENERGY BALANCE.
MT=103,107
CALCULATED BY USING THE GNASH CODE/1,12/.
MF=13 GAMMA-RAY PRODUCTION CROSS SECTIONS (ABOVE 5.80993 MEV)
MT=3
CALCULATED BY THE STATISTICAL MODEL AND COUPLED-CHANNEL MODEL,
USING THE GNASH CODE /12/ AND THE ECIS /9/ OR JUPITOR-1 CODE
/10/. BRANCHING RATIOS FOR TRANSITIONS BETWEEN DISCRETE LEVELS
WERE TAKEN FROM REF./3/. GAMMA-RAY TRANSITION STRENGTH IN THE
CONTINUUM WAS CALCULATED BY THE BRINK-AXEL GIANT RESONANCE
MODEL FOR E1 TRANSITION AND BY THE WEISSKOPF SINGLE-PARTICLE
MODEL FOR E2 AND M1 TRANSITION/1/.
MF=14 GAMMA-RAY ANGULAR DISTRIBUTIONS
MT=3,51-70,102,103,107
ISOTROPIC DISTRIBUTION WAS ASSUMED.
MF=15 GAMMA-RAY SPECTRA
MT=3,102,103,107
CALCULATED WITH THE GNASH CODE/1,12/
REFERENCES
1) KITAZAWA H. ET AL.: PROC. INT. CONF. NUCLEAR DATA FOR
SCIENCE AND TECHNOLOGY, MITO, 1988, P.473, (1988).
2) CHIBA S. ET AL.: JAERI-M 92-027, P.35 (1992).
3) YAMAMURO N.: JAERI-M 90-006 (1990).
4) KUMABE I. ET AL.: NUCL. SCI. ENG., 104, 280 (1990).
5) ENSDF: EVALUATED NUCLEAR STRACTURE DATA FILE.
6) NAKAGAWA T.: JAERI-M 84-192 (1984).
7) MUGHABGHAB S.F. ET AL.: "NEUTRON CROSS SECTIONS, VOL. 1
PART A", ACADEMIC PRESS (1981).
8) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
9) RAYNAL J.: COMPUTER PROGRAM ECIS79 FOR COUPLED-CHANNEL
CALCULATIONS, 1979 (UNPUBLISHED).
10) TAMURA T.: REV. MOD. PHYS., 37, 679 (1965).
11) ENDT P.M. AND VAN DER LEUN C.: NUCL. PHYS., A310, 1 (1978).
12) YOUNG P.G. AND ARTHUR E.D.: LA-6947 (1977).
13) KITAZAWA H. ET AL.: UNPUBLISHED.
14) KITAZAWA H.: COMPUTER PROGRAM HIKARI FOR DIRECT-SEMIDIRECT
CAPTURE CALCULATIONS, 1980 (UNPUBLISHED).
15) VONACH H.: NUCLEAR DATA STANDARDS FOR NUCLEAR MEASUREMENTS,
IAEA TECHNICAL REPORTS SERIES NO. 227 (1983).