92-U -238
92-U -238 KYU,JAERI+ EVAL-APR87 Y.KANDA ET AL.
DIST-SEP89 REV2-MAR94
----JENDL-3.2 MATERIAL 9237
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-01 SIMULTANEOUS EVALUATION FOR FISSION AND CAPTURE CROSS
SECTIONS WAS COMPLETED IN THE ENERGY RANGE ABOVE 50 KEV.
87-04 OTHER QUANTITIES WERE EVALUATED BY
Y. KANDA AND Y. UENOHARA (KYUSHU UNIV.): MF'S = 3, 4 AND 5
ABOVE RESONANCE REGION.
T. NAKAGAWA (JAERI) : RESOLVED RESONANCE PARAMETERS AND
BACKGROUND CROSS SECTIONS.
K. HIDA (NAIG) : DATA FOR GAMMA-RAY PRODUCTION.
88-03 DATA OF TOTAL, ELASTIC, INELASTIC (MT=59,60) AND CAPTURE
CROSS SECTIONS WERE PARTLY MODIFIED.
89-03 DATA OF TOTAL, ELASTIC, INELASTIC AND CAPTURE CROSS SECTIONS
WERE MODIFIED. UNRESOLVED RESONANCE PARAMETERS WERE ALSO
MODIFIED. FP YIELDS WERE ADDED.
94-03 JENDL-3.2.
INELASTIC SCATTERING AND (N,3N) CROSS SECTIONS RE-EVALUATED
BY Y.KANDA AND T.KAWANO (KYUSHU UNIV.)/1/
RESOLVED RESONANCE PARAMETERS MODIFIED BY T.NAKAGAWA(JAERI)
UNRESOLVED RESONANCE PARAMETERS MODIFIED BY Y.KIKUCHI(JAERI)
FISSION SPECTRA CALCULATED BY T.OHSAWA(KINKI UNIV.)
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(2,151) RESOLVED AND UNRESOLVED RESONANCE PARAMETERS
UP TO 150 KEV
(3,2), (3,4), (3,17), (3,51-91)
MAINLY INELASTIC SCATTERING CROSS SECTIONS.
(4,51-83)
(5,18) NEW CALCULATION CONSIDERING MULTI-CHANCE
FISSION.
(5,91) CONTRIBUTION FROM PRECOMPOUND PROCESS ADDED.
(12,51-57) BASED ON NEWLY ADOPTED LEVEL SCHEME.
(13,3), (15,3), (12,102), (15,102) LOWEST ENERGY OF MT=3
WAS CHANGED TO 934.74 KEV
***********************************************************
MF=1 GENERAL INFORMATION
MT=451 DESCRIPTIVE DATA AND DIRECTORY RECORDS
MT=452 NUMBER OF NEUTRONS PER FISSION
SUM OF MT'S= 455 AND 456
MT=455 DELAYED NEUTRON DATA
TAKEN FROM REF./2/.
MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION
TAKEN FROM EVALUATION BY FREHAUT /3/.
MF=2 RESONANCE PARAMETERS
MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS
1) RESOLVED RESONANCE PARAMETERS FOR MLBW FORMULA
(RESOLVED RESONANCE REGION = 1.0E-5 EV TO 10 KEV)
PARAMETERS WERE ADOPTED FROM JEF-2 EVALUATION /4/ AND THE
ENERGY RANGE WAS DIVIDED INTO 10 INTERVALS BY ASSUMING
HYPOTHETICAL RESONANCES OUTSIDE EACH INTERVAL. PARAMETERS
OF THE HYPOTETICAL RESONANCES WERE DETERMINED BY MEANS OF
SAMMY/5/.
2) UNRESOLVED RESONANCE PARAMETERS
(UNRESOLVED RESONANCE REGION = 10 KEV TO 150 KEV)
PARAMETERS WERE OBTAINED WITH THE PARAMETER FITTING CODE
ASREP/6/ SO AS TO REPRODUCE THE CROSS SECTIONS EVALUATED IN
THIS ENERGY REGION.
2200-M/S CROSS SECTIONS AND CALCULATED RESONANCE INTEGRALS.
2200 M/S(B) RES. INTEG.(B)
TOTAL 12.077
ELASTIC 9.360
FISSION 11.8E-6 1.72
CAPTURE 2.717 277.
MF=3 NEUTRON CROSS SECTIONS
BELOW 10 KEV, NO BACKGROUND CROSS SECTIONS WERE GIVEN.
ABOVE 10 KEV, CROSS SECTIONS WERE EVALUATED AS FOLLOWS, AND
THEY WERE REPRESENTED WITH THE UNRESOLVED RESONANCE
PARAMETERS EXCEPT THE FISSION CROSS SECTION.
MT=1 TOTAL
THE SAME AS JENDL-2 WHICH WERE BASED ON THE FOLLOWING
EXPERIMENTAL DATA.
BELOW 500 KEV: UTTLEY ET AL./7/, WHALEN ET AL./8/.
POENITZ ET AL./9/, TSUBONE ET AL./10/
0.5 - 4.5 MEV: POENITZ ET AL./9/, TSUBONE ET AL./10/,
KOPSCH ET AL./11/.
4.5 - 15 MEV : FOSTER AND GLASGOW /12/
15 - 20 MEV : BRATENAHL ET AL./13/, PETERSON ET
AL./14/.
MT=2 ELASTIC SCATTERING
CALCULATED AS (TOTAL)-(PARTIAL CROSS SECTIONS)
MT=4, 51-83, 91 TOTAL AND PARTIAL INELASTIC SCATTERING
CROSS SECTIONS WERE CALCULATED BY TAKING ACCOUNT OF DIRECT
AND COMPOUND PROCESSES.
1) DIRECT PROCESS
COUPLED-CHANNEL MODEL CODE ECIS88/15/ WAS USED FOR CALCULA-
TION OF DIRECT INELASTIC CROSS SECTIONS TO THE EXCITED LEVELS
WHICH BELOG TO THE VIBRATIONAL BANDS AND THE GROUND STATE
ROTATIONAL BAND. FOR THE LEVELS OF MT = 65, 68, 73, 76 AND
77, THE DIRECT CROSS SECTIONS WERE NOT INCLUDED. THE OPTICAL
POTENTIAL PARAMETERS WERE TAKEN FROM REF./16/.
V0=46.2 - 0.3E, WS = 3.6 + 0.4E, VSO = 6.2 (MEV)
R = 1.26, RS=1.26, RSO=1.12 (FM)
A = 0.63, AS=0.52, ASO=0.47 (FM)
BETA-2 =0.198, BETA-4 =0.057
THE BAND COUPLING STRENGTH (BETA) WAS DETERMINED FROM THE
EXPERIMENTAL CROSS SECTION DATA/17, 18, 19, 20, 21/ AND
DDX DATA/22/.
2) COMPOUND PROCESS:
COMPOUND INELASTIC SCATTERING CROSS SECTIONS TO THE 1ST AND
2ND LEVELS WERE CALCULATED WITH ECIS88/15/. THOSE TO THE
OTHER LEVELS WERE CALCULATED USING HAUSER-FESHBACH-MOLDAUER
(HFM) THEORY/23/. THE OPTICAL POTENTIAL PARAMETERS/24/
USED IN HFM CALCULATION ARE AS FOLLLOWS:
V0 = 50.378-0.354E-27.073(N-Z)/A, (MEV)
WS = 9.265-0.232E+0.03318E**2-12.666(N-Z)/A, (MEV)
VSO= 6.2, (MEV)
R = 1.264, A = 0.612, (FM)
RS = 1.256, AS = 0.553+0.0144E, (FM)
RSO= 1.1, ASO= 0.75 (FM)
IN ORDER TO GET BETTER AGREEMENT WITH EXPERIMENTAL DATA OF
THE TOTAL INELASTIC SCATTERING CROSS SECTION/22, 25, 26/, A
FACTOR OF 0.91 WAS MULTIPLIED TO THE CALCULATED COMPOUND
PROCESS CROSS SECTION EXCEPT FOR THE FIRST LEVEL.
LEVEL SCHEME /27/
--------------------
NO. ENERGY(MEV) SPIN-PARITY
G.S. 0.0 0 +
1 0.044910 2 +
2 0.14841 4 +
3 0.30721 6 +
4 0.6801 1 -
5 0.7319 3 -
6 0.8267 5 -
7 0.9257 0 +
8 0.9308 1 -
9 0.9502 2 -
10 0.9673 2 +
11 0.993 0 +
12 0.9975 3 -
13 1.0373 2 +
14 1.0566 4 +
15 1.0595 3 +
16 1.0603 2 +
17 1.1057 3 +
18 1.1126 1 -
19 1.127 4 +
20 1.1287 2 -
21 1.168 4 +
22 1.1704 3 -
23 1.2242 2 +
24 1.2326 4 -
25 1.2692 6 +
26 1.2785 1 -
27 1.2858 5 -
CONTINUUM LEVELS WERE ASSUMED ABOVE 1.29 MEV.
THE FOLLOWING HYPOTHETICAL LEVELS WERE INTRODUCED SO AS TO
REPRODUCE WELL THE MEASURED DDX DATA/22/.
28 1.5
29 2.0
30 2.5
31 3.0
32 3.5
33 4.0
MT=16 (N,2N)
SMOOTH CROSS SECTION WAS DETERMINED ON THE BASIS OF FREHAUT
ET AL./28/ BELOW 15 MEV, AND VEESER ET AL./25/ AND KARIUS ET
AL./29/ ABOVE 15 MEV.
MT=17 (N,3N)
BASED ON VEESER ET AL./30/ ABOVE 16 MEV, RENORMALIZED SO
THAT CONSISTENCY MIGHT BE KEPT AMONG FISSION, CAPTURE, (N,2N)
AND INELASTIC SCATTERING CROSS SECTIONS.
MT=18 FISSION
BELOW 100 KEV : TAKEN FROM EXPERIMENTAL DATA /31/.
100 - 600 KEV : EVALUATED ON THE BASIS OF THE DATA OF
DIFFILIPPO ET AL. /32/, BEHRENS AND CARLSON /33/,
NORDBORG ET AL. /34/ AND MEADOWS /35,36/.
ABOVE 600 KEV : RESULTS OF SIMULTANEOUS EVALUATION /37/ MADE
BY CONSIDERING THE EXPERIMENTAL DATA OF REFS./33,34,
35,36,38,39,40,41,42,43,44,45,46,47/.
MT=102 CAPTURE
BELOW 300 KEV, EVALUATION WAS MAINLY BASED ON THE DATA
MEASURED BY KAZAKOV ET AL./48/. ABOVE 300 KEV, DATA WERE
TAKEN FROM JENDL-2 WHICH WERE DETERMINED MAINLY FROM THE
MEASUREMENTS BY POENITZ /47/, PANITKIN AND SHERMAN /49/,
MOXON /50/, FRICKE ET AL. /51/ AND MENLOVE AND POENITZ
/52/. AT HIGH ENERGIES, SLIGHT MODIFICATION WAS MADE.
MT=251 MU-L BAR
CALCULATED FROM THE ANGULAR DISTRIBUTIONS IN MF=4, MT=2.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2 CALCULATED WITH ECIS/53/, CASTHY/54/ AND
ELIESE-3/55/.
MT=51,52 CALCULATED WITH ECIS88/15/.
MT=53-64,66,67,69-72,74,75
CALCULATED WITH ECIS88, HAUSER-FESHBACH-MOLDAUER
(HFM) THEORY.
MT=65,68,73,76,77
CALCULATED WITH HFM THEORY.
MT=16,17,18,91 ASSUMED TO BE ISOTROPIC IN THE LAB. SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17 EVAPORATION SPECTRUM.
MT=91 CALCULATED WITH GNASH/56/.
MT=18
DISTRIBUTIONS WERE CALCULATED WITH THE MODIFIED MADLAND-NIX
MODEL/57,58/. THE COMPOUND NUCLEUS FORMATION CROSS SECTIONS
FOR FISSION FRAGMENTS (FF) WERE CALCULATED USING BECHETTI-
GREENLEES POTENTIAL/59/. UP TO 4TH-CHANCE-FISSION WERE
CONSIDERED AT HIGH INCIDENT NEUTTRON ENERGIES. THE IGNATYUK
FORMULA/60/ WERE USED TO GENERATE THE LEVEL DENSITY
PARAMETERS.
PARAMETERS ADOPTED:
TOTAL AVERAGE FF KINETIC ENERGY = 167.41 - 172.65 MEV
AVERAGE ENERGY RELEASE = 186.115 - 186.364 MEV
AVERAGE MASS NUMBER OF LIGHT FF = 99 - 111
AVERAGE MASS NUMBER OF HEAVY FF = 128 - 140
LEVEL DENSITY OF THE LIGHT FF = 10.106 - 10.963
LEVEL DENSITY OF THE HEAVY FF = 11.441 - 7.811
RATIO OF NUCLEAR TEMPERATURE
FOR LIGHT TO HEAVY FF = 1.0
NOTE THAT THE PARAMETERS VARY WITH THE INCIDENT ENERGY
WITHIN THE INDICATED RANGE.
MT=455
TAKEN FROM SAPHIER ET AL. /61/
MF=12 PHOTON PRODUCTION MULTIPLICITIES (OPTION 1)
GIVEN FOR THE FOLLOWING SECTIONS BELOW 934.74 KEV.
MT=18 FISSION
THE THERMAL NEUTRON-INDUCED FISSION GAMMA SPECTRUM OF U-235
MEASURED BY VERBINSKI /62/ WAS ADOPTED FOR THE WHOLE ENERGY
REGION. THE INTENSITY OF PHOTON BELOW 0.14 MEV, WHERE NO
DATA WERE GIVEN, WAS ASSUMED TO BE THE SAME AS THAT BETWEEN
0.14 AND 0.3 MEV.
MT=51-57 INELASTIC
PHOTON BRANCHING DATA WERE TAKEN FROM REF./63/, AND
CONVERTED TO PHOTON MULTIPLICITIES.
MT=102 CAPTURE
CALCULATED WITH GNASH/56/. IN THE CASE WHERE THE OBTAINED
MULTIPLICITIES WERE TOO LARGE, THEY WERE RENORMALIZED BY
USING ENERGY BALANCE.
MF=13 PHOTON PRODUCTION CROSS SECTIONS
MT=3 NON-ELASTIC
PHOTON PRODUCTION CROSS SECTION CALCULATED WITH GNASH /56/
WERE GROUPED INTO THE NON-ELASTIC IN THE ENERGY RANGE ABOVE
934.74 KEV. TRANSMISSION COEFFICIENTS FOR INCIDENT CHANNEL
WERE GENERATED WITH ECIS/53/, AND THOSE FOR EXIT CHANNEL
WITH ELIESE-3/55/. THE DATA FOR FISSION WERE BASED ON THE
MEASURED U-235 SPECTRA /62/. FURTHER DETAILS ARE GIVEN IN
REF./64/
MF=14 ANGULAR DISTRIBUTIONS OF PHOTONS
ISOTROPIC DISTRIBUTIONS WERE ASSUMED FOR ALL SECTIONS.
MF=15 CONTINUOUS PHOTON ENERGY SPECTRA
MT=3 NON-ELASTIC
CALCULATED WITH GNASH /56/.
MT=18 FISSION
U-235 SPECTRA MEASURED BY VERBINSKI/62/.
MT=102 CAPTURE
CALCULATED WITH GNASH/56/.
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