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9.424200+4 2.399790+2 1 1 2 0
0.000000+0 1.000000+0 0 0 0 6
1.000000+0 2.000000+7 0 0 10 31
0.000000+0 0.000000+0 0 0 335 1
94-Pu-242 ENEA,IJS EVAL-OCT98 A.VENTURA, S.MASETTI, A.TRKOV
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 9446
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
******************************************************************
05-01 NEA/OECD (Rugama) 8 delayed neutron groups
Jefdoc-976(Spriggs,Campbel and Piksaikin,Prg Nucl Eng 41,223(2002)
***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- JENDL-3.2 (DIST-SEP89)
MODIFICATIONS BY A. Ventura, S.Masetti, A.Trkov
Fission energy from ENDF/B-VI
******************************************************************
HISTORY
THE DATA IN THE PRESENT FILE ARE EVALUATED BY:
A.VENTURA, S.MASETTI ENEA NUCLEAR DATA CENTRE, BOLOGNA, ITALY
A.TRKOV JOZEF STEFAN INSTITUTE, LJUBLJANA, SLOVENIA
THE EVALUATION IS BASED ON JENDL-3.2, WITH CHANGES IN THE
FOLLOWING SECTIONS:
MF=1 MT=456 Number of propmt neutrons emitted by fission
A. Nouri (Data Bank) June 1999
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).
Modification of MT=1 MT=452 for the two first
energies to be the sum of MT=455 and 456
MF=2 MT=151 ------- RESOLVED RESONANCE REGION UP TO 5.7 KEV
MF=3 MT=16 -------- (N,2N)
MF=3 MT=17 -------- (N,3N)
MF=3 MT=18 -------- (N,FISSION)
MF=3 MT=51-70 ----- (N,N' DISCRETE LEVELS)
MF=3 MT=91 -------- (N,N' CONTINUUM)
MF=12 ------------- PHOTON PRODUCTION MULTIPLICITIES
MF=15 ------------- CONTINUOUS PHOTON ENERGY SPECTRA
A COMPLETE CHECK OF ALL REACTION CHANNELS IN THE ENERGY RANGE
FROM 40 KEV UP TO 20 MEV HAS BEEN MADE AS FOLLOWS:
MF=3
MT=1,2
TOTAL AND REACTION CROSS SECTION, AS WELL AS DIRECT CONTRIBUTIONS
TO THE EXCITATION OF THE 0+, 2+, 4+, 6+, LEVELS OF THE GROUND
STATE BAND, HAVE BEEN CALCULATED IN COUPLED CHANNELS
APPROXIMATION BY MEANS OF THE DEFORMED OPTICAL MODEL PARAMETRIZED
BY G. VLADUCA ET AL. (REF-A). THE RESULTING TOTAL CROSS SECTION
IS IN GOOD AGREEMENT WITH EXPERIMENTAL DATA AND JENDL-3.2
EVALUATION. THE ORIGINAL DATA ARE NOT CHANGED. THE ELASTIC CROSS
SECTION IS ADJUSTED FOR CONSISTENCY BETWEEN THE TOTAL AND THE
REVISED PARTIAL CROSS SECTIONS
MF=3
MT=18
THE FISSION CROSS SECTION (INCLUDING FIRST, SECOND AND THIRD
CHANCE CONTRIBUTIONS) HAS BEEN CALCULATED WITH THE FISSION
BARRIER PARAMETERS GIVEN IN (REF-A) AND CONSTANT TEMPERATURE
FORMULA FOR THE LEVEL DENSITIES AT THE SADDLE POINTS, WITH
PARAMETERS ADJUSTED ON THE EXPERIMENTAL FISSION DATA.
THE RESULTING CROSS SECTION IS IN SATISFACTORY AGREEMENT WITH
EXPERIMENTS IN THE FISSION CONTINUUM, AND HAS BEEN USED TO
COMPUTE FISSION COMPETITION WITH N,XN CHANNELS (X=1,2,3).
IN THE FILE, THE EVALUATED CROSS SECTION HAS BEEN REPLACED BY
A BEST FIT TO THE EXPERIMENTAL FISSION CROSS SECTION
IN THE ENERGY RANGE FROM 200 KEV UP TO 20 MEV:
IN THE 200 KEV - 9 MEV RANGE, THE REFERENCE DATA ARE
THOSE BY WEIGMANN ET AL. (REF-B); FROM 9 MEV TO 20 MEV,
THE DATA BY BEHRENS ET AL. (REF-C) HAVE BEEN NORMALIZED TO
WEIGMANN ET AL. AT 9 MEV. BELOW 200 KEV THE JENDL-3.2
EVALUATION HAS BEEN MAINTAINED.
MF=3
MT=16,17
THE (N,2N) AND (N,3N) CROSS SECTIONS HAVE BEEN CALCULATED
CONSISTENTLY WITH THE FISSION COMPETITION, TAKING INTO
ACCOUNT COMPOUND NUCLEUS AND PREEQUILIBRIUM CONTRIBUTIONS.
IN THE COMPOUND NUCLEUS CALCULATIONS, THE LEVEL DENSITIES
OF THE NEUTRON CHANNELS ARE GIVEN BY THE COMPOSITE GILBERT-
CAMERON FORMULA, WITH PARAMETERS ADJUSTED ON THE CUMULATIVE
NUMBER OF DISCRETE LEVELS AND THE AVERAGE SPACING OF S-WAVE
NEUTRON RESONANCES; THE PREEQUILIBRIUM CALCULATIONS HAVE BEEN
PERFORMED WITH A STANDARD EXCITON MODEL WITH EXCITON LEVEL
DENSITIES GIVEN BY WILLIAMS FORMULA WITH PARAMETERS FROM
SYSTEMATICS.
MF=3
MT=51-70,91
THE INELASTIC CROSS SECTIONS FOR EXCITATION OF 20 DISCRETE
LEVELS AND THE CONTINUUM HAVE BEEN TAKEN FROM MASLOV ET AL.
(REF-D). DIRECT ELASTIC AND DIRECT INELASTIC FOR MT= 51, 52,
53 AND OPTICAL TRANSMISSION COEFFICIENTS FROM COUPLED CHANNEL
CALCULATIONS. THREE LEVELS OF ROTATIONAL GROUND STATE BAND
ARE COUPLED.THE ADOPTED LEVEL SCHEME IS TAKEN FROM NUCLEAR
DATA SHEETS.
MF=12,15
MT=16,17,91,102
GAMMA RAY MULTIPLICITIES AND SPECTRA FOR INELASTIC, CAPTURE,
(N,2N) AND (N,3N) CHANNELS HAVE BEEN CALCULATED BY MEANS OF
THE PENELOPE CODE (REF-E).
AFTER THE PROBABILITY FOR COMPOUND NUCLEUS FORMATION HAS BEEN
COMPUTED FOR ALL POSSIBLE J'S AND PARITIES, THE CODE DETERMINES
THE GAMMA-RAY DECAY PROBABILITIES IN J AND PARITY FOR EACH STEP
OF EACH GAMMA GAMMA-RAY CASCADE STORY. AFTER SUMMATION OVER ALL
J'S AND PARITIES, AND CONSIDERING THE ELECTROMAGNETIC SELECTION
RULES, ALL SINGLE STEP CONTRIBUTIONS ARE LUMPED TOGETHER INTO
ENERGY BINS ACCORDING TO THE ENERGIES OF EMITTED GAMMA RAYS.
IN THE CALCULATION OF GAMMA-RAY CASCADES IT IS ASSUMED THAT
ONLY E1 TRANSITIONS ARE POSSIBLE BETWEEN CONTINUUM LEVELS, AND
ALSO FOR TRANSITIONS FROM CONTINUUM TO DISCRETE LEVELS.
FOR THE TRANSITIONS BETWEEN DISCRETE LEVELS, EXPERIMENTAL
GAMMA-RAY DECAY SCHEMES AND BRANCHING RATIOS HAVE BEEN USED.
REFERENCES:
A) G. VLADUCA, M. SIN AND A. TUDORA, REPORT NEA/SEN/NSC/WPPR(96)5
B) H. WEIGMANN ET AL., NUCL.PHYS. A438,333(1985)
C) J.W. BEHRENS ET AL.,NUCL.SC.ENG.66,433(1978)
D) V.M. MASLOV ET AL., REPORT INDC(BLR)-010(1997)
E) G. REFFO AND F. FABBRI, PENELOPE CODE (UNPUBLISHED)
THE DESCRIPTION OF THE ORIGINAL JENDL-3.2 FILE FOLLOWS
*** *** *** *** *** *** *** *** *** *** *** *** *** *** *** ***
87-05 EVALUATION WAS MADE BY
T.MURATA (NAIG): CROSS SECTIONS ABOVE RESONANCE REGION AND
OTHER QUANTITIES,
M.KAWAI (NAIG): RESONANCE PARAMETERS.
89-02 FP YIELDS WERE ADDED.
COMPILATION WAS MADE BY 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)
***********************************************************
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
BASED ON THE EXPERIMENTAL DATA BY EVANS ET AL./1/, AND
SYSTEMATICS BY TUTTLE/2/, BENEDETTI ET AL./3/ AND WALDO ET
AL./4/ DECAY CONSTANTS WERE EVALUATED BY BRADY AND
ENGLAND/5/.
MT=456 PROMPT NEUTRONS PER FISSION
BASED ON SYSTEMATICS BY MANERO AND KONSHIN/6/, AND BY
HOWERTON/7/.
MF=2 RESONANCE PARAMETERS
MT=151 RESONANCE PARAMETERS
RESOLVED RESONANCE PARAMETERS FOR MLBW ( 1.0E-5 EV TO 1.15 KEV)
EVALUATION FOR JENDL-2 WAS MODIFIED ON THE BASIS OF FISSION
CROSS SECTION MEASUREMENTS BY WEIGMANN ET AL. /8/
RES. ENERGIES = BNL 325 (3RD) /9/
NEUTRON AND CAPTURE WIDTHS = POORTMANS ET AL. /10/,
AUCHAMPAUGH ET AL./11/
FISSION WIDTHS = WEIGMANN ET AL. /8/
R = 9.9 FM
AVERAGE CAPTURE WIDTH = 0.0242 EV
TWO NEGATIVE RESONANCES WERE ADDED TO REPRODUCE 2200-M/S
CROSS SECTIONS RECOMMENDED BY MUGHABGHAB /12/
UNRESOLVED RESONANCE PARAMETERS ( 1.15 TO 40 KEV)
PARAMETERS WERE DETERMINED TO REPRODUCE CROSS SECTIONS
EVALUATED AS DESCRIBED BELOW.
CALCULATED 2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200-M/S(B) RES. INTEG.(B)
TOTAL 27.11 ----
ELASTIC 8.32 ----
FISSION 0.00256 5.58
CAPTURE 18.79 1130
MF=3 NEUTRON CROSS SECTIONS
BELOW 40 KEV, REPRESENTED WITH RESONANCE PARAMETERS.
MT=1 SIG-TOT
BELOW 6 KEV : EXPERIMENTAL DATA OF YOUNG AND REEDER /13/
WERE AVERAGED OVER SOME KEV ENERGY INTERVAL.
ABOVE 6 KEV : SPLINE FITTING TO EXPERIMENTAL DATA OF
KAEPPELER ET AL. /14/ AND MOORE ET AL. /15/
MT=2 SIG-EL
OBTAINED BY SUBTRACTING OTHER CROSS SECTIONS FROM TOTAL.
MT=4 SIG-INEL
SUM OF PARTIAL INELASTIC CROSS SECTIONS
MT=51-91 PARTIAL SIG-INEL
BELOW 3 MEV : THE RESULTS OF STATISTICAL AND COUPLED CHANNEL
CALCULATION OF LAGRANGE ET AL./16/ WERE ADOPTED.
ABOVE 3 MEV : EXTRAPOLATION OF THE VALUES WAS MADE BASED
ON DWBA CALCULATION.
LEVEL SCHEME
NO. ENERGY(MEV) SPIN-PARITY
G.S. 0.0 0 +
1 0.04285 2 +
2 0.141685 4 +
3 0.294314 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 1.223 2 +
23 1.2325 4 +
24 1.2408 1 -
25 1.2621 3 +
26 1.2820 3 -
27 1.30873 5 -
28 1.41079 0 +
LEVELS ABOVE 1.41079 MEV WERE ASSUMED TO BE CONTINUUM.
MT=16,17,37 SIGMAS OF (N,2N), (N,3N) AND (N,4N)
GIVEN BY MULTIPLICATION OF NEUTRON EMISSION CROSS SECTION
AND BRANCHING RATIO TO EACH REACTION. THE NEUTRON EMISSION
CROSS SECTION WAS OBTAINED BY SUBTRACTING FISSION AND
CAPTURE CROSS SECTIONS FROM REACTION CROSS SECTION
CALCULATED WITH SPHERICAL OPTICAL MODEL. THE BRANCHING
RATIO WAS CALCULATED WITH THE FORMALISM GIVEN BY SEGEV ET
AL./17/
MT=18 SIG-FISS
BELOW 100 KEV : SHAPE OF SIG-FISS DETERMINED ON THE FISSION
AREA DATA OF AUCHAMPAUGH ET AL./18/ THEN NORMALIZED TO
THE VALUE OF HIGHER ENERGY REGION.
ABOVE 100 KEV : FISSON RATIO TO U-235 WAS DETERMINED ON THE
EXPERIMENTAL DATA OF BEHRENS ET AL./19/ AND MULTIPLIED BY
U-235 FISSION CROSS SECTION /20/.
MT=102 SIG-CAP
ENERGY REGION OF 6 KEV TO 210 KEV : DETERMINED ON THE BASIS OF
EXPERIMENTAL DATA OF HOCHENBURY ET AL./21/ AND WISSHAK AND
KAEPPELER /22/.
OTHER ENERGY REGION : STATISTICAL CALCULATION RESULT WITH
CASTHY CODE /23/ WAS NORMALIZED TO SIG-CAP IN THE REGION OF
6 TO 210 KEV. DIRECT AND COLLECTIVE CAPTURE PROCESSES WERE
INCLUDED IN HIGH ENERGY REGION USING THE VALUE OF U-238
GIVEN BY KITAZAWA ET AL./24/
** PARAMETERS FOR THE CASTHY CODE CALCULATION
SPHERICAL OPTICAL POTENTIAL PARAMETERS
V=40. 1-0.05EN , WS=6.5+0.15EN , VSO=7.0 (MEV)
R=1.32 , RS=1.38 , RSO=1.32 (FM)
A=AS=ASO=0.47 (FM)
LEVEL DENSITY PARAMETERS WERE DETERMINED TO REPRODUCE THE
RESONANCE LEVEL SPACINGS AND LEVEL SCHEME SUM STAIRCASES.
MT=251 MU-L
ASSUMED TO BE THE SAME AS THAT OF PU-240.
MF=4 ANGULAR DISTRIBUTIONS
THE SAME DISTRIBUTIONS AS PU-240 WERE ASSUMED, WHICH WERE
DETERMINED AS FOLLOWS.
MT=2 DSIG-EL
SPHERICAL OPTICAL MODEL CALCULATION
MT=51 TO 91 DSIG-INEL
FOR THE 1ST AND 2ND LEVELS THE RESULTS OF CALCULATION OF
LAGRANGE ET AL./16/ ARE AVAILABLE AND THEIR RESULTS WERE
ADOPTED. FOR OTHER LEVELS, STATISTICAL PLUS DWBA CALCU-
LATIONS WERE MADE.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17 AND 91
DISTRIBUTIONS WERE CALCULATED WITH PEGASUS/25/
MT=37
EVAPORATION SPECTRUM WAS TAKEN FROM JENDL-2
MT=18
TAKEN FROM JENDL-2. TEMPERATURE WAS ESTIMATED FROM Z**2/A
SYSTEMATICS BY SMITH ET AL. /26/
REFERENCES
1) EVANS,A.E. ET AL.: NUCL. SCI. ENG., 50, 80 (1973).
2) TUTTLE,R.J.: INDC(NDS)-107/G+SPECIAL, P.29 (1979),
3) BENEDETTI,G. ET AL.: NUCL. SCI. ENG., 80, 379 (1982).
4) WALDO,R. ET AL.: PHYS. REV., C23, 1113 (1981).
5) BRADY,M.C. AND ENGLAND,T.R.: NUCL. SCI. ENG., 103, 129 (1989).
6) MANERO,F. AND KONSHIN,V.A.: AT. ENERGY REV.,10, 637 (1972).
7) HOWERTON,R.J.: NUCL. SCI. ENG., 62, 438 (1977).
8) WEIGMANN,H., WARTENA,J.A. AND BURKHOLZ,C. : NUCL. PHYS.,
A438, 333 (1985).
9) MUGHABGHAB,S.F. AND GARBER,D.I. : BNL 325, 3RD ED., VOL. 1
(1973)
10) POORTMANS,F. ET AL. : NUCL. PHYS., A207, 342 (1973).
11) AUCHMPAUGH,G.F. AND BOWMAN,C.D. : PHYS. REV., C7, 2085 (1973).
12) MUGHABGHAB,S.F. : "NEUTRON CROSS SECTIONS", VOL. 1, PART B,
ACADEMIC PRESS (1984).
13) YOUNG,T.E. AND REEDER,S.D. : NUCL. SCI. ENG., 40, 389 (1970).
14) KAEPPELER,F. ET AL. : PROC. OF MEETING ON NUCLEAR DATA OF
HIGHER PU AND AM ISOTOPEPS FOR REACTOR APPLICATION, P.49
(1978, BNL).
15) MOORE,M.S. ET AL. : PROC. OF NUCLEAR CROSS SECTIONS FOR
TECHNOLOGY, P.703 (1979, KNOXVILLE).
16) LAGRANGE,CH. AND JARY,J. : NEANDC(E) 198"L" (1978).
17) SEGEV,M. ET AL. : ANNALS OF NUCL. ENERGY, 5, 239 (1978).
18) AUCHAMPAUGH,G.F. ET AL. : NUCL. PHYS., A171, 31 (1971).
19) BEHRENS,J.W. ET AL. : NUCL. SCI. ENG., 66, 433 (1978).
20) MATSUNOBU,H. ET AL. : EVALUATION FOR JENDL-3 (1987).
21) HOCKENBURY,R.W. ET AL. : NBS SPECIAL PUBLICATION 425, VOL. 2,
P.584 (1975).
22) WISSHAK,K. AND KAEPPELER,F. : NUCL. SCI. ENG., 66, 363 (1978),
NUCL. SCI. ENG., 69, 39 (1979).
23) IGARASI,S. AND FUKAHORI,T.: JAERI 1321 (1991).
24) KITAZAWA,H. ET AL. : NUCL. PHYS., A307, 1 (1978).
25) IIJIMA,S. ET AL. : JAERI-M 87-025, P.337 (1987).
26) SMITH,A.B. ET AL.: ANL/NDM-50 (1979).
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