95-AM-244 JAERI EVAL-MAR88 T.NAKAGAWA
JAERI-M 89-008 DIST-MAR02 REV2-FEB02 20020222
----JENDL-3.3 MATERIAL 9552
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
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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.
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HISTORY
88-03 EVALUATED FOR JENDL-3 WAS MADE BY T.NAKAGAWA (JAERI)/1/.
MF=1 GENERAL INFORMATION
MT=451 COMMENT AND DICTIONARY
MT=452 NUMBER OF NEUTRONS PER FISSION
SUM OF NU-P (MT=456) AND NU-D (MT=455).
MT=455 DELAYED NEUTRON DATA
ESTIMATED FROM SEMI-EMPIRICAL FORMULA BY TUTTLE /2/.
MT=456 NUMBER OF PROMPT NEUTRONS
ESTIMATED FROM SEMI-EMPIRICAL FORMULA BY HOWERTON/3/.
MF=2,MT=151 RESONANCE PARAMETERS
NO RESONANCE PARAMETERS WERE GIVEN.
2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200 M/S VALUE RES. INT.
TOTAL 2912. B -
ELASTIC 11.62 B -
FISSION 2300. B 1260 B
CAPTURE 600. B 316 B
MF=3 NEUTRON CROSS SECTIONS
MT=1 TOTAL CROSS SECTION
BELOW 0.07 EV, SUM OF PARTIAL CROSS SECTIONS. ABOVE 0.07
EV, CALCULATED WITH OPTICAL AND STATISTICAL MODEL CODE
CASTHY/4/. THE SAME OPTICAL POTENTIAL PARAMETERS AS THOSE
FOR AM-242 WHICH WERE OBTAINED /5/ BY FITTING THE DATA OF
PHILLIPS AND HOWE /6/ FOR AM-241, AND MODIFIED A LITTLE.
V = 42.0 - 0.107*EN (MEV)
WS= 9.0 - 0.339*EN + 0.0531*EN**2 (MEV)
VSO = 7.0 (MEV)
R = RSO = 1.282 , RS = 1.29 (FM)
A = ASO = 0.60 , B = 0.5 (FM)
MT=2 ELASTIC SCATTERING CROSS SECTION
CALCULATED WITH CASTHY/4/.
MT=4,51-75,91 INELASTIC SCATTERING CROSS SECTIONS
CALCULATED WITH CASTHY/4/. THE LEVEL SCHEME WAS TAKEN
FROM REF. /7/
NO ENERGY(KEV) SPIN-PARITY
G.S. 0 6 -
1 88.0 1 +
2 100.309 2 +
3 123.281 3 +
4 148.283 4 +
5 175.657 1 -
6 183.511 5 -
7 197.295 2 -
8 228.299 3 -
9 261.696 2 -
10 272.202 4 -
11 289.212 1 -
12 296.658 3 -
13 322.751 5 -
14 355.575 0 -
15 342.650 3 -
16 343.658 4 -
17 348.405 3 +
18 361.838 2 -
19 377.057 0 +
20 390.028 4 +
21 398.743 5 -
22 414.689 2 +
23 418.957 2 +
24 420.131 2 +
25 421.204 3 -
LEVELS ABOVE 435 KEV WERE ASSUMED TO BE OVERLAPPING.
THE LEVEL DENSITY PARAMETERS WERE DETERMINED ON THE BASIS
OF NUMBER OF EXCITED LEVELS/8/ AND RESONANCE LEVEL
SPACING/9/.
AM-245 AM-244
A(1/MEV) 31.3 30.3
T(MEV) 0.360 0.340
C(1/MEV) 18.06 26.47
E-X(MEV) 3.265 2.373
SPIN-CUTOFF(1/MEV**0.5) 31.98 31.39
PAIRING E(MEV) 0.39 0.0
MT=16,17,37 (N,2N), (N,3N) AND (N,4N) REACTION CROSS SECTIONS
CALCULATED WITH EVAPORATION MODEL.
MT=18 FISSION CROSS SECTION
BELOW 0.07 EV, 1/V SHAPED CROSS SECTION WAS NORMALIZED TO
2300 +- 300 B AT 0.0253 EV/9/. ABOVE 0.07 EV, THE CROSS
SECTION WAS ASSUMED TO BE THE SAME AS THAT OF AM-242G
(MAT=3952 OF JENDL-3).
MT=102 CAPTURE CROSS SECTION
BELOW 0.07 EV, 1/V CROSS SECTION WAS NORMALIZED TO 600 B
AT 0.0253 EV THAT WAS ESTIMATED BY ASSUMING THE SAME CROSS
SECTION RATIO AS HIGHER ENERGY REGION. ABOVE 0.07 EV,
CALCULATED WITH CASTHY/4/. THE GAMMA-RAY STRENGTH
FUNCTION WAS DETERMINED FROM D-OBS=0.13 EV CALCULATED FROM
LEVEL DENSITY PARAMETERS AND WG=0.05 EV.
MT=251 MU-L BAR
CALCULATED WITH CASTHY/4/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-75,91
LEGENDRE COEFFICIENTS WERE GIVEN BY THE OPTICAL AND
STATISTICAL MODEL CALCULATION.
MT=16,17,18,37
ISOTROPIC DISTRIBUTIONS IN THE LABORATORY SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,37,91
EVAPORATION SPECTRUM WITH NUCLEAR TEMPERATURE CALCULATED
FROM LEVEL DENSITIES.
MT=18
MAXWELLIAN FISSION SPECTRUM ESTIMATED FROM Z**2/A
SYSTEMATICS BY SMITH ET AL./10/.
REFERENCES
1) NAKAGAWA T.: JAERI-M 89-008 (1989).
2) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL , P.29 (1979).
3) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438 (1977).
4) IGARASI S.: J. NUCL. SCI. TECHNOL., 12, 67 (1975).
5) IGARASI S. AND NAKAGAWA T.: JAERI-M 8342 (1979).
6) PHILLIPS T.W. AND HOWE R.E.: NUCL. SCI. ENG., 69, 375 (1979).
7) SHURSHIKOV E.N.: NUCL. DATA SHEETS, 49, 785 (1986).
8) ENSDF, EVALUATED NUCLEAR STRUCTURE DATA FILE (1988).
9) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL. 1, PART B",
ACADEMIC PRESS, INC. (1984).
10) SMITH A.B.: ANL/NDM-50 (1979).