29-CU- 65 NAIG,MAPI EVAL-MAR87 N.YAMAMURO,T.KAWAKITA
DIST-SEP89 REV2-SEP93
----JENDL-3.2 MATERIAL 2931
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 EVALUATION WAS PERFORMED FOR JENDL-3.
87-05 COMPILED BY K.SHIBATA (JAERI).
93-09 JENDL-3.2.
(3,1),(3,2),(3,102) MODIFIED BY T.NAKAGAWA(JAERI)
(12,102),(15,102) MODIFIED BY S.IGARASI(NEDAC)
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(2,151) UPPER BOUNDARY ENERGY CHANGED TO 50 KEV
(3,1),(3,2) 50 KEV - 153 KEV
(3,102) 50 KEV - 20 MEV
(4,16-32),(4,91) TAKEN FROM JENDL FUSION FILE
(5,16-91) TAKEN FROM JENDL FUSION FILE
(12,102),(15,102)
***********************************************************
-------------------------------------------------------------
JENDL FUSION FILE /1/ (AS OF SEP. 1993)
EVALUATED BY B.YU(CIAE) AND S.CHIBA (NDC/JAERI)
COMPILED BY B.YU
CROSS SECTIONS WERE TAKEN FROM JENDL-3.1. MF=6 (DDX'S)
OF MT=16, 22, 28, 32 AND 91 WERE CREATED WITH F15TOB
PROGRAM /1/. MODIFIED KUMABE'S SYSTEMATICS /1/ WAS USED.
THE PRECOMPOUND/COMPOUND RATIO WAS CALCULATED BY THE
SINCROS-II CODE SYSTEM/2/.
OPTICAL-MODEL, LEVEL DENSITY AND OTHER PARAMETERS USED
IN THE SINCROS-II CALCULATION ARE DESCRIBED IN REF./2/.
LEVEL SCHEMES WERE DETERMINED ON THE BASIS OF ENSDF/3/.
-------------------------------------------------------------
MF=1 GENERAL INFORMATION
MT=451 DESCRIPTIVE DATA AND DICTIONARY
MF=2 RESONANCE PARAMETERS
MT=151 RESOLVED RESONANCE PARAMETERS FOR MLBW FORMULA
PARAMETERS WERE MAINLY TAKEN FROM THE WORK OF MUGHABGHAB
ET AL./4/
RESONANCE REGION : 1.0E-5 EV TO 50 KEV.
UPPER BOUNDARY OF THE RESONANCE REGION WAS CHANGED FROM
153 KEV OF JENDL-3.1 TO 50 KEV BECAUSE SERIOUS LEVEL
MISSING WAS FOUND ABOVE 50 KEV.
SCATTERING RADIUS: 6.70 FM
CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS
2200-M/S RES. INTEG.
ELASTIC 14.073 B -
CAPTURE 2.168 B 2.22 B
TOTAL 16.242 B -
MF=3 NEUTRON CROSS SECTIONS
MT=1 TOTAL
50 TO 250 KEV : BASED ON THE MEASURED DATA OF ROHR ET
AL./5/ THE DATA WERE SMOOTHED WITH 5%
RESOLUTION.
0.3 TO 3 MEV : BASED ON THE EXPERIMENTAL DATA OF NATURAL
ELEMENT/6,7/.
3 TO 20 MEV : OPTICAL-MODEL CALCULATION WITH CASTHY/8/.
THE OPTICAL POTENTIAL PARAMETERS USED ARE AS
FOLLOWS/9/ (IN THE UNITS OF MEV AND FM):
V = 51.725 - 0.447*E R0 = 1.221 A0 = 0.683
WS = 8.44 + 0.055*E RS = 1.223 AS = 0.507
(DERIVATIVE WOODS-SAXON FORM)
VSO= 8.0 RSO= 1.221 ASO = 0.683
MT=2 ELASTIC SCATTERING
(TOTAL) - (REACTION CROSS SECTION)
MT=4,51-70,91 INELASTIC SCATTERING
STATISTICAL MODEL CALCULATIONS WERE MADE WITH CASTHY/8/
BELOW 3 MEV BY TAKING ACCOUNT OF COMPETING PROCESSES, AND
WITH GNASH/10/ ABOVE 3 MEV INCLUDING PREEQUILIBRIUM
EFFECTS. THE DIRECT-PROCESS COMPONENT WAS CONSIDERED FOR
THE LEVELS OF MT=51-54,64,91 BY THE DWBA CALCULATIONS WITH
DWUCK/11/. THE LEVEL SCHEME WAS TAKEN FROM REF./12/.
NO. ENERGY(MEV) SPIN-PARITY
G.S. 0.0 3/2 -
1. 0.7706 1/2 -
2. 1.1160 5/2 -
3. 1.4820 7/2 -
4. 1.6230 5/2 -
5. 1.7250 3/2 -
6. 2.0940 7/2 -
7. 2.1070 5/2 -
8. 2.2130 1/2 -
9. 2.2780 7/2 -
10. 2.3290 3/2 -
11. 2.4070 9/2 -
12. 2.5260 9/2 +
13. 2.5330 5/2 -
14. 2.5340 7/2 +
15. 2.5930 1/2 -
16. 2.6440 9/2 -
17. 2.6500 5/2 -
18. 2.6550 5/2 -
19. 2.6690 5/2 -
20. 2.7530 9/2 +
LEVELS ABOVE 2.80 MEV WERE ASSUMED TO BE OVERLAPPING.
MT=16,22,28,32,103,104,107 (N,2N),(N,N'A),(N,N'P),(N,N'D),(N,P)
(N,D) AND (N,A) CROSS SECTIONS
CALCULATED WITH GNASH/10/.
OPTICAL POTENTIAL PARAMETERS FOR PROTON, ALPHA-PARTICLES
AND DEUTERON WERE AS FOLLOWS/13,14,15/.
PROTON
V = 59.11 - 0.55*E R0 = 1.25 A0 = 0.65
WS = 10.4 RS = 1.25 AS = 0.47
VSO= 7.5 RSO= 1.25 ASO= 0.47
ALPHA-PARTICLE
V = 164.7 R0 = 1.442 A0 = 0.52
WV = 22.4 RV = 1.442 AV = 0.52
RC = 1.30
DEUTERON
V = 106.69 R0 = 1.05 A0 = 0.86
WS = 13.92 RS = 1.43 AS = 0.704
VSO= 7.0 RSO= 0.75 ASO= 0.5
RC = 1.3
MT=102 RADIATIVE CAPTURE CROSS SECTION
BELOW 1.505 MEV, CALCULATION WITH CASTHY WAS ADOPTED. A
VALUE OF 0.001 WAS EMPLOYED FOR THE GAMMA-RAY STRENGTH
FUNCTION FOR S-WAVE NEUTRONS. ABOVE THIS ENERGY, CROSS
SECTION CURVE WAS BASED ON THE EXPERIMENTAL DATA/16, 17,
18/. 0.5MB WAS ASSUMED AT 14 MEV.
MT=251 MU-BAR
CALCULATED WITH CASTHY.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-70
CALCULATED WITH CASTHY FOR EQUILIBRIUM PROCESS. THE
COMPONENTS OF THE DIRECT PROCESS WERE ADDED TO THE LEVELS
OF MT=51-54,64 BY USING THE DWUCK CODE /11/.
MT=16, 22, 28, 32, 91
TAKEN FROM JENDL FUSION FILE.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16, 22, 28, 32, 91
TAKEN FROM JENDL FUSION FILE.
MF=12 PHOTON PRODUCTION MULTIPLICITIES
MT=16,22,28,32,91,103,104,107
CALCULATED WITH GNASH.
MT=51-70
TRANSITION PROBABILITIES ARE GIVEN.
MT=102
OBTAINED FROM ENERGY BALANCE.
MF=14 PHOTON ANGULAR DISTRIBUTIONS
MT=16,22,28,32,51-70,91,102,103,104,107
ASSUMED TO BE ISOTROPIC.
MF=15 PHOTON ENERGY DISTRIBUTIONS
MT=16,22,28,32,91,103,104,107
CALCULATED WITH GNASH.
MT=102
CALCULATED WITH CASTHY.
REFERENCES
1) CHIBA S. ET AL.: JAERI-M 92-027, P.35 (1992).
2) YAMAMURO N.: JAERI-M 90-006 (1990).
3) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE, BNL/NNDL.
4) MUGHABGHAB S.F., DIVADEENAM M. AND HOLDEN N.E.: "NEUTRON CROSS
SECTIONS, VOL. 1, PART A", ACADEMIC PRESS (1981).
5) ROHR G. ET AL.: EANDC(E)-89, P.1 (1968), EXFOR 20151003.
6) FOSTER JR., D.G. AND GLASGOW D.W.: PHYS. REV., C3, 576 (1971).
7) WHALEN J.F. ET AL.: ANL-7710, 12 (1971).
8) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
9) HETRICK D.M., FU C.Y. AND LARSON D.C.: "CALCULATED NEUTRON-
INDUCED CROSS SECTIONS FOR CU-63,65 FROM 1 TO 20 MEV AND
COMPARISONS WITH EXPERIMENTS", ORNL/TM-9083 (1984).
10) YOUNG P.G. AND ARTHUR E.D.: "GNASH, A PREEQUILIBRIUM,
STATISTICAL NUCLEAR-MODEL CODE FOR CALCULATION OF CROSS
SECTIONS AND EMISSION SPECTRA", LA-6974 (1977).
11) KUNZ P.D.: UNIV. COLORADO (1974).
12) WARD N.J. AND TULI J.K.: NUCL. DATA SHEETS, 47, 135 (1986).
13) PEREY F.G.: PHYS. REV. 131, 745 (1963).
14) MCFADDEN L. AND SATCHLER G.R.: NUCL. PHYS. 84, 177 (1966).
15) LOHR J.M. AND HAEBERLI W.: NUCL. PHYS. A232, 381 (1974).
16) ZAIKIN G.G. ET AL.: ATOM. ENERGIJA, 10, 508(1961). EXFOR40248
17) JOHNSRUD A.E. ET AL.: PHYS. REV., 116, 927 (1959). EXFOR11675
18) VOIGNIER J. ET AL.: NUCL. SCI. ENG., 93, 43(1986). EXFOR22006