94-Pu-238 MAPI,JAERI EVAL-MAR89 T.KAWAKITA, T.NAKAGAWA
DIST-JAN09 20090105
----JEFF-311 MATERIAL 9434
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
** **
** Original data taken from: JEFF-3.1 **
** **
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***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
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05-01 NEA/OECD (Rugama) 8 delayed neutron groups
Jefdoc-976 (Wilson and England, Prog Nucl Eng 41,71(2002)
***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- JENDL-3.2 (DIST-SEP89 REV2-JUN94)
Unresolved resonance parameters
from BROND-2.2
ENDF/B-VI for MT=458 (fission energy)
Fission Q value modified accordignly
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HISTORY
79-03 NEW EVALUATION WAS MADE BY T.KAWAKITA (PNC).
89-03 RE-EVALUATION WAS MADE BY T.KAWAKITA (MAPI) AND
T.NAKAGAWA(JAERI).
94-06 JENDL-3.2.
NU-P, NU-D AND NU-TOTAL WERE MODIFIED.
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(1,452), (1,455), (1,456)
***********************************************************
***** MODIFIED PARTS FOR JEFF-3.0 ********************
A. Nouri (Data Bank) June 1999
MF=1 MT=456 Number of propmt neutrons emitted by fission
use the same representation as for MT=452
(ENDF-6 recommendation): convert LNU=1
(polynomial (linear) representation) used in
JENDL-32 to tabular representation (LNU=2).
MF=2 MT=151 Add unresolved resonance parameters from BROND-2.2
***********************************************************
MF=1 GENERAL INFORMATION
MT=451 COMMENT AND DICTIONARY
MT=452 NUMBER OF NEUTRONS PER FISSION
SUM OF NU-P NAD NU-D.
MT=455 DELAYED NEUTRONS PER FISSION
AVERAGE VALUES OF SYSTEMATICS BY TUTTLE/1/, BENEDETTI ET
AL./2/ AND WALDO ET AL./3/ DECAY CONSTANTS WERE EVALUATED
BY BRADY AND ENGLAND/4/.
MT=456 PROMPT NEUTRONS PER FISSION
THE THERMAL VALUE OF PROMPT NEUTRONS WAS BASED ON EXPERI-
MENTAL DATA OF JAFFEY AND LERNER /5/, KROSHKIN ET AL./6/
AND HADDAD AND ASGHER/7/. THE ENERGY DEPENDENT TERM WAS
ESTIMATED FROM HOWRTON'S FORMULA /8/.
MF=2 RESONANCE PARAMETERS
MT=151 RESOLVED RESONANCE PARAMETERS FOR MLBW FORMULA.
ENERGY RANGE IS FROM 1.0E-5 EV TO 500 EV. PARAMETERS WERE
TAKEN FROM THE FOLLOWING EXPERIMENTAL DATA.
49 RESONANCES ABOVE 10 EV : SILBERT /9/
4 RESONANCES BELOW 10 EV : YOUNG /10/
THE PARAMETERS OF TWO NEGATIVE AND 2.9-EV RESONANCES WERE
ADJUSTED TO THE THERMAL CROSS SECTIONS/11/.
CALCULATED 2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200-M/S RES. INTEG.
TOTAL 586.7 B -
ELASTIC 28.53 B -
FISSION 17.89 B 32.7 B
CAPTURE 540.3 B 154 B
MF=3 NEUTRON CROSS SECTIONS
THE ENERGY REGION BELOW 500 EV IS THE RESONANCE REGION. ABOVE
500 EV, THE CROSS SECTIONS WERE EVALUATED AS FOLLOWS.
MT=1,2,4,51-78,91,102 TOTAL, ELASTIC AND INELASTIC SCATTERING,
AND CAPTURE CROSS SECTIONS
CALCULATED WITH OPTICAL AND STATISTICAL MODELS. CASTHY/12/
WAS USED FOR THE CALCULATION.
OPTICAL POTENTIAL PARAMETERS:
THE REAL POTENTIAL WAS ADJUSTED SO AS TO OBTAINED THE
REASONABLE COMPOUND NUCLEUS FORMATION CROSS SECTION. THE
OTHER PARAMETERS WERE TAKEN FROM MURATA'S EVALUATION /13/.
V = 38.8 - 0.05*EN (MEV)
WS = 6.5 + 0.15*EN (MEV)
VSO= 7.0 (MEV)
A = B = ASO= 0.47 (FM)
R = RSO= 1.32 (FM)
RS = 1.52 (FM)
THE LEVEL SCHEME:
TAKEN FROM REF. /14/.
NO. ENERGY(KEV) SPIN-PARITY
G.S. 0.0 0 +
1 44.08 2 +
2 145.98 4 +
3 303.4 6 +
4 514.0 8 +
5 605.1 1 -
6 661.4 3 -
7 763.2 5 -
8 941.5 0 +
9 962.77 1 -
10 968.2 2 -
11 983.0 2 +
12 985.5 2 -
13 1028.55 2 +
14 1069.95 3 +
15 1082.57 4 -
16 1125.8 4 +
17 1174.5 2 +
18 1202.7 3 -
19 1228.6 0 +
20 1264.2 2 +
21 1310.3 2 +
22 1426.6 0 +
23 1447.3 1 -
24 1458.5 2 +
25 1560.0 1 -
26 1596.5 2 +
27 1621.4 1 -
28 1636.6 1 -
CONTINUUM LEVELS ASSUMED ABOVE 1.65 MEV.
THE LEVEL DENSITY PARAMETERS OF GILBERT AND CAMERON /15/.
THE FISSION, (N,2N) AND (N,3N) CROSS SECTIONS WERE TAKEN
INTO ACCOUNT AS THE COMPETING PROCESSES. FOR THE CAPTURE
CROSS SECTION, THE GAMMA-RAY STRENGTH FUNCTION WAS ESTIMATED
FROM D-OBS = 9.5EV AND AVERAGE RADIATIVE WIDTH = 0.04 EV.
MT=16,17 (N,2N) AND (N,3N) REACTION CROSS SECTIONS
CALCULATION BASED ON THE PEARLSTEIN'S METHOD /16/.
MT=18 FISSION CROSS SECTION
EVALUATED MAINLY ON THE BASIS OF DATA MEASURED BY
BUDTZ-JORGENSEN/17/. OTHER EXPERIMENTS /9, 18, 19, 20, 21,
22, 23, 24, 25/ WERE ALSO TAKEN INTO CONSIDERATION.
MT=251 MU-BAR
CALCULATED WITH OPTICAL MODEL.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-78,91
CALCULATED WITH OPTICAL MODEL.
MT=16,17,18
ISOTROPIC IN THE LABORATORY SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,91
EVAPORATION SPECTRUM WAS ASSUMED.
MT=18
MAXWELLIAN TYPE FISSION SPECTRUM. TEMPERATURE WAS ESTIMATED
FROM Z**2/A SYSTEMATICS BY SMITH ET AL. /26/.
REFERENCES
1) R.J. TUTTLE: INDC(NDS)-107/G+SPECIAL, P.29 (1979),
2) G. BENEDETTI ET AL.: NUCL. SCI. ENG., 80, 379 (1982).
3) R. WALDO ET AL.: PHYS. REV., C23, 1113 (1981).
4) M.C. BRADY AND T.R. ENGLAND: NUCL. SCI. ENG., 103, 129 (1989).
5) A.H. JAFFEY AND J.L. LERNER: NUCL. PHYS., A145, 1 (1970).
6) N.I. KROSHKIN ET AL.: ATOMNAJA ENERGIJA, 29, 95 (1970).
= EXFOR40064007.
7) M. HADDAD AND M. ASGHAR: 1988 MITO, P.979 (1988).
8) R.J. HOWERTON: NUCL. SCI. ENG., 62, 438 (1977).
9) M.G. SILBERT ET AL.: NUCL. SCI. ENG., 52, 176 (1973).
10) T.E. YOUNG ET AL.: NUCL. SCI. ENG., 30, 355 (1967).
11) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL. 1, PART B",
ACADEMIC PRESS (1984).
12) S. IGARASI AND T. FUKAHORI: JAERI 1321 (1991).
13) T. MURATA: PRIVATE COMMUNICATION.
14) C.M. LEDERER ET AL.: TABLE OF ISOTOPES, 7TH ED. (1978).
15) A. GILBERT AND A.G.W. CAMERON: CAN. J. PHYS., 43, 1446 (1965).
16) S. PEARLSTEIN: NUCL. SCI. ENG., 23, 238 (1965).
17) C. BUDTZ-JORGENSEN ET AL.: 1982 ANTWERP, 206 (1983).
18) D.M. BARTON AND P.G. KOONTY: PHYS. REV., 162, 1070 (1967).
19) E.F. FOMUSHKIN ET AL.: SOV. J. NUCL. PHYS., 5, 689 (1967).
20) S.B. ERMAGAMBETOV AND G.N. SHIRENKIN: SOV. J. NUCL. PHYS.,
25, 1364 (1968).
21) D.M. DRAKE ET AL.: LA-4420, P.101 (1970).
22) S.B. ERMAGAMBETOV ET AL.: SOV. J. NUCL. ENERGY,29, 1190(1970).
23) E.F. FOMUSHKIN ET AL.: SOV. J. NUCL. PHYS., 10, 529 (1970).
24) D.L. SHPAK ET AL.: JETP LETTERS, 15, 228 (1972).
25) B. ALAM ET AL.: NUCL. SCI. ENG., 99, 267 (1988).
26) A.B. SMITH ET AL.: ANL/NDM-50 (1979).
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