94-Pu-240
94-PU-240 NAIG+ EVAL-MAY87 T.MURATA, A.ZUKERAN
DIST-SEP89 REV2-AUG93
----JENDL-3.2 MATERIAL 9440
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-05 EVALUATION WAS MADE BY
T.MURATA (NAIG) : CROSS SECTIONS ABOVE RESONANCE REGION
AND OTHER QUANTITIES,
A.ZUKERAN(HITACHI): RESONANCE PARAMETERS.
88-06 MT'S=16, 17, 37 AND 102 WERE MODIFIED.
89-02 FP YIELDS WERE TAKEN FROM JNDC FP DECAY FILE VERSION-2.
COMPILATION WAS MADE BY T. NAKAGAWA (JAERI).
90-07 FP YIELD DATA WERE MODIFIED.
90-10 MF=5, MT=16, 17, 91: MODIFIED AT THRESHOLD ENERGIES.
93-08 JENDL-3.2.
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(1,452), (1,455)
***********************************************************
MF=1 GENERAL INFORMATION
MT=451 COMMENTS AND DICTIONARY
MT=452 NUMBER OF NEUTRONS PER FISSION
SUM OF MT=455(DELAYED NEUTRONS) AND MT=456(PROMPT NEUTRONS).
MT=455 DELAYED NEUTRON DATA
BELOW 5 MEV, NU-D OF 0.00911 MEASURED BY BENEDETTI ET AL.
/1/ WAS ADOPTED. ABOVE 6 MEV, 0.0067 WAS GIVEN ON THE BASIS
OF TUTTLE'S SYSTEMATICS /2/. DECAY CONSTANTS WERE TAKEN
FROM EVALUATION BY BARDY AND ENGLAND /3/.
MT=456 NUMBER OF PROMPT NEUTRONS
LINEAR LEAST-SQUARES FITTING TO THE EXPERIMENTAL DATA OF
FREHAUT ET AL. /4/ RENORMALIZED TO CF-252 NU-P=3.756.
MF=2 RESONANCE PARAMETERS
MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS
1) RESOLVED RESONANCES FOR MLBW FORMULA (1.0E-5 TO 4 KEV)
PARAMETERS OF A NEGATIVE AND THE 1.057-EV RESONANCES WERE
REVISED ON THE BASIS OF RECOMMENDATION BY MUGHABGHAB /5/.
NEUTRON AND CAPTURE WIDTHS OF OTHER LEVELS WERE BASED ON THE
EXPERIMENTAL DATA BY HOCKENBURY ET AL. /6/ IN THE ENERGY
RANGE FROM 20 TO 500 EV, AND KOLAR AND BOECKHOFF /7/ FROM
500 EV TO 4 KEV. THE AVERAGE CAPTURE WIDTH OF 29.5 MILLI-EV
WAS ASSUMED FOR THE RESONANCES WHOSE CAPTURE WIDTHS WERE
UNKNOWN. BELOW 610 EV, THE SUB-THRESHOLD FISSION WIDTHS
WERE CALCULATED FROM THE AREA DATA BY WESTON AND TODD /8/.
ABOVE 610 EV, THEY WERE TAKEN FROM THE DATA BY AUCHAMPAUGH
AND WESTON /9/.
2) UNRESOLVED RESONANCES (4 TO 40 KEV)
ENERGY DEPENDENT PARAMETERS WERE DETERMINED TO REPRODUCE THE
EVALUATED CROSS SECTIONS IN THIS ENERGY REGION. FISSION
WIDTHS WERE ADJUSTED TO AVERAGE CROSS SECTIONS MEASURED BY
WESTON AND TODD /8/.
CALCULATED 2200-M/SEC CROSS SECTIONS AND RES. INTEGERALS.
2200-M/SEC RES. INTEG.
TOTAL 291.13 B
ELASTIC 1.644 B -
FISSION 0.0588 B 8.94 B
CAPTURE 289.4 B 8110. B
MF=3 NEUTRON CROSS SECTIONS
BELOW 4 KEV: BACKGROUND CROSS SECTIONS ARE GIVEN TO THE CAPTURE
CROSS SECTION.
ABOVE 4 KEV: EVALUATED AS FOLLOWS. IN THE ENERGY RANGE FROM 4
TO 40 KEV, THE CROSS SECTIONS ARE REPRESENTED WITH
THE UNRESOLVED RESONANCE PARAMETERS, AND THE BACK-
GROUND CROSS SECTIONS ARE GIVEN IN MF=3.
MT=1 TOTAL
EVALUATED WITH SPLINE FITTING TO THE EXPERIMENTAL DATA OF
SMITH ET AL./10/, KAEPPELER ET AL./11/ AND POENITZ ET
AL./12/
MT=2 ELASTIC SCATTERING
OBTAINED BY SUBTRACTING THE OTHER CROSS SECTIONS FROM TOTAL
CROSS SECTION.
MT=4 TOTAL INELASTIC SCATTERING
SUM OF PARTIAL INELASTIC SCATTERING CROSS SECTIONS (MT=51
TO MT=91).
MT=51-78, 91 PARTIAL INELASTIC SCATTERING
BELOW 3 MEV, THE RESULTS OF STATISTICAL AND COUPLED-CHANNEL
CALCULATION MADE BY LAGRANGE ET AL. /13/ WERE ADOPTED. FOR
SOME LEVELS, FOR WHICH SMITH'S EXPERIMENTAL DATA /14/ WERE
AVAILABLE, THE CALCULATED RESULTS WERE NORMALIZED (FOR 1ST,
2ND, 3RD, 5TH AND 9 TO 11TH LEVELS).
LEVEL SCHEME
NO. ENERGY(MEV) SPIN-PARITY
G.S. 0.0 0 +
1 0.04285 2 +
2 0.14169 4 +
3 0.29431 6 +
4 0.4976 8 +
5 0.59736 1 -
6 0.64889 3 -
7 0.74232 5 -
8 0.8607 0 +
9 0.90032 2 +
10 0.93807 1 -
11 0.95887 2 -
12 0.9924 4 +
13 1.0018 3 -
14 1.0306 3 +
15 1.0375 4 -
16 1.0764 4 +
17 1.0895 0 +
18 1.1155 5 -
19 1.1370 2 +
20 1.1615 6 -
21 1.1778 3 +
22 1.2230 2 +
23 1.2325 4 +
24 1.2408 2 -
25 1.2621 3 +
26 1.2820 3 -
27 1.30873 5 -
28 1.41079 0 +
LEVELS ABOVE 1.4108 MEV WERE ASSUMED TO BE CONTINUUM.
MT=16,17,37 (N,2N),(N,3N) AND (N,4N)
CALCULATED FROM NEUTRON EMISSION CROSS SECTION AND BRANCHING
RATIO TO EACH REACTION CHANNEL. NEUTRON EMISSION CROSS
SECTION WAS OBTAINED BY SUBTRACTING THE FISSION AND CAPTURE
CROSS SECTIONS FROM COMPOUND NUCLEUS FORMATION CROSS SECTION
CALCULATED WITH SPHERICAL OPTICAL MODEL. BRANCHING RATIO
WAS OBTAINED FROM FORMALISM GIVEN BY SEGEV ET AL. /15/
MT=18 FISSION
BELOW 100 KEV: AVERAGE VALUES OF FISSION CROSS SECTION
MEASURED BY WESTON AND TODD /8/ WERE NORMALIZED TO THE
VALUE AT 100 KEV OF THE SIMULTANEOUS EVALUATION.
ABOVE 100 KEV: SIMULTANEOUS EVALUATION WAS MADE BY TAKING
ACCOUNT OF EXPERIMENTAL DATA OF FISSION RATIO AND ABSOLUTE
CROSS SECTIONS OF U-235, U-238, PU-239, PU-240 AND PU-241,
AND CAPTURE CROSS SECTION OF AU-197 /16/.
MT=102 CAPTURE
BELOW 350 KEV: BASED ON THE EXPERIMENTAL DATA OF HOCKENBURY ET
AL. /6/, WESTON AND TODD /17/ AND THE RATIO DATA OF WISSHAK
AND KAEPPELER /18/ WITH THE CAPTURE CROSS SECTION OF AU-197
/16/. AS A GUIDE LINE, STATISTICAL MODEL CALCULATION WAS
MADE WITH CASTHY CODE /19/.
ABOVE 350 KEV: THE STATISTICAL MODEL CALCULATION WAS
NORMALIZED TO THE VALUE AT 350 KEV. DIRECT AND COLLECTIVE
CAPTURE WAS INCLUDED IN HIGH ENERGY REGION ADOPTING THE
VALUE FOR U-238 GIVEN BY KITAZAWA ET AL. /20/.
THE SPHERICAL OPTICAL POTENTIAL PARAMETERS
V = 40.6 - 0.05*EN, WS = 6.5 + 0.15*EN (MEV)
VSO= 7.0 (MEV)
R = RSO =1.32 , RS = 1.38 (FM)
A = AS = ASO =0.47 (FM)
LEVEL DENSITY PARAMETERS WERE DETERMINED TO REPRODUCE THE
RESONANCE LEVEL SPACINGS AND STAIRCASES OF DISCRETE LEVELS.
MT=251 MU-BAR
THE SAME AS JENDL-1 /21/ EXCEPT FOR 20 MEV.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2
TAKEN FROM JENDL-1 /21/.
MT=16,17,18,37,91
ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.
MT=51-78
FOR THE 1ST AND 2ND LEVELS, RESULTS OF LAGRANGE ET AL. /13/
WERE ADOPTED. FOR OTHERS, STATISTICAL AND DWBA CALCULATIONS
WERE MADE.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,91
CALCULATED WITH PRE-COMPOUND AND MULTI-STEP EVAPORATION
THEORY CODE PEGASUS /22/.
MT=37
EVAPORATION SPECTRUM WAS GIVEN.
MT=18 FISSION SPECTRA
CALCULATED FROM MADLAND-NIX FORMULA /23/.
AVERAGE ENERGY RELEASE = 199.179 MEV
TOTAL AVERAGE FF KINETIC ENERGY = 177.53 MEV
AVERAGE MASS NUMBER OF LIGHT FF = 101
AVERAGE MASS NUMBER OF HEAVY FF = 140
LEVEL DENSITY PARAMETER = A/10.0
MT=455 DELAYED NEUTRON SPECTRA
ASSUMED TO BE THE SAME AS PU-239 WHICH WERE TAKEN FROM THE
EVALUATION BY SAPHIER ET AL. /24/.
REFERENCES
1) BENEDETTI G., ET AL.: NUCL. SCI. ENG., 80, 379 (1982).
2) TUTTLE R.J.: INDC(NDS)-107/G-SPECIAL, P.29 (1979).
3) BRADY M.C. AND ENGLAND T.R.: NUCL. SCI. ENG., 103, 129(1989).
4) FREHAUT J., ET AL.: CEA(R) 4626 (1974).
5) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL. 1, PART B",
ACADEMIC PRESS (1984).
6) HOCKENBURY R.W. ET AL.: NUCL. SCI. ENG., 49, 153 (1972).
7) KOLAR W. AND BOECKHOFF K.H.: J. NUCL. ENERGY, 22, 299 (1968).
8) WESTON L.W. AND TODD J.H.: NUCL. SCI. ENG., 88, 567 (1984).
9) AUCHAMPAUGH G.F. AND WESTON L.E.: PHYS. REV., C12, 1850
(1975).
10) SMITH A.B. ET AL.: NUCL. SCI. ENG., 47, 19 (1972).
11) KAEPPLER F., ET AL.: PROC. OF MEETING ON NUCLEAR DATA OF
HIGHER PU AND AM ISOTOPES FOR REACTOR APPLICATION, HELD AT
BNL, P.49 (1978)
12) POENITZ W.P., ET AL.; NUCL. SCI. ENG., 78, 333 (1981), AND
ANL/NDM-80 (1983).
13) LAGRANGE CH. AND JARY J.: NEANDC(E) 198"L" (1978).
14) SMITH A.B., ET AL.: IAEA-153, P.447 (1973).
15) SEGEV M., ET AL.: ANNALS OF NUCL. ENERGY, 5, 239 (1978).
16) KANDA Y. ET AL.: 1985 SANTA FE, 2, 1567 (1986).
17) WESTON L.W. AND TODD J.H.: NUCL. SCI. ENG.,63, 143 (1977).
18) WISSHAK K. AND KAEPPELER F.: NUCL. SCI. ENG., 66, 363 (1978)
AND NUCL. SCI. ENG., 69, 39 (1979).
19) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
20) KITAZAWA H., ET AL.: NUCL. PHYS., A307, 1 (1978).
21) IGARASI S., ET AL.: JAERI 1261 (1979).
22) IIJIMA S., ET AL.: JAERI-M 87-025, P.337 (1987).
23) MADLAND D.G. AND NIX J.R.: NUCL. SCI. ENG., 81, 213 (1982).
24) SAPHIER D., ET AL.: NUCL. SCI. ENG., 62, 660 (1977).