95-Am-243
95-Am-243 MINSK,JAERIEVAL-JAN02 V.M. Maslov+, T.Nakagawa
INDC(BLR)-006+ DIST-MAR02 REV2-FEB02 20020202
----JENDL-3.3 MATERIAL 9549
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
77-03 New evaluation was made by S.Igarasi and T.Nakagawa/Ig77/
82-03 Complete reevaluation for JENDL-2 was made by
Y.Kikuchi/Ki82/
88-03 Reevaluation for JENDL-3 was made by T.Nakagawa /Na89/
00-03 JENDL-3.3 was compiled by T.Nakagawa
Evaluated data of Maslov et al. /Ma96/ were extensively
adopted.
02-01 Resonance parameters and Nu-d were modified.
***** Modified parts from JENDL-3.2 *******************
All data
*******************************************************
=================================================================
Description on modified parts from Maslov's evaluation.
=================================================================
MF=1 General information
MT=452 Total number of neutrons per fission
Sum of MT=455 and 456.
MT=455 Delayed neutrons
Nu-d were based on the data of Charlton et al./Ch97/,
Saleh et al. /Sa97/ and Brady and England /Br89/.
Decay constants were taken from Saleh et al. and Brady and
England.
MF=2 Resonance Rapameters
MT=151
Resolved resonance parameters (up to 250 eV)
Background cross section was given to fission so as to
reproduce the thermal cross section of 0.0813 +- 0.025 b
measured by Kobayashi et al. /Ko99/
Fission width of levels around 10 - 50 eV was modified so
as to reproduce the measured fission cross secion /Ko99/.
Unresolved resonance parameters (250 eV - 42.3751 keV)
The level spacing was modified to keep consistency with
that of L=0 and J=2.0. The neutron width was also modified
with the same factor as the level spacing. Interpolation
of cross sections was changed to 5 (log-log).
The fission width was maltiplied by a factor of 0.8 to 1.0
to agree with the recent experimental data /Ko99/.
Calculated Thermal cross sections and Resonance integral
at 0.0253 eV (b) Res. Integ. (b)
Total 84.25 -
Elastic 7.464 -
Fission 0.0813 7.54
Capture 76.71 1790
MF=3 Neutron Cross Sections
MT=2 elastic
Calculated as Total - partial cross sections.
MT=18 Fission
Above 500 keV, JENDL-3.2 was adopted because JENDL-3.2 was in
better agreement with experimental data than Maslov's
evaluation. Between 42.375 keV to 500 keV, the cross section
was determined by eye-guiding.
NOTE: The data of MT's=19, 20 and 21 calculated by Maslov et
al. /Ma96/ were not adopted.
MT=102 Capture
Direct and semi-direct capture cross section was calculated
with DSD code /Ka99/, and added to Maslov's calculation.
MF=5 Energy Distributions of Secondary Neutrons
MT=16, 17, 91
At the threshold energies, the same shape of distributions at
the second incident energy was assumed. Interpolation was
replaced with 22.
MT=455
Results of summation calculation made by Brady and England
/Br89/ were adopted. Abundances obtained by Saleh et al./Sa97/
were adopted.
Other parts are the same as Maslov's evaluation.
References
Br89) Brady M.C. and England T.R.: Nucl. Sci. Eng., 103, 129
(1989).
Ch97) Charlton W., et al. 1997 Trieste, Part I, p.491 (1997)
Ig77) Igarasi S. and Nakagawa T.: JAERI-M 7174 (1977).
Ka99) Kawano T.: private communication (1999).
Ki82) Kikuchi Y.: JAERI-M 82-096 (1982).
Ko99) Kobayashi K. et al.: J. Nucl. Sci. Technol., 36, 20 (1999).
Ma96) Maslov V.M. et al.: INDC(BLR)-006 (1996).
Na89) Nakagawa T.: JAERI-M 89-008 (1990).
Sa97) Saleh H.H., et al.: Nucl. Sci. Eng., 125, 51 (1997).
========== Description given in Maslov's data ===================
95-Am-243 MINSK BYEL EVAL-JUL96
DIST-SEPTEMBER96
V.M. MASLOV, E.Sh. SUKHOVITSKIJ,
Yu.V. PORODZINSKIJ, A.B. KLEPATSKIJ,
G.B. MOROGOVSKIJ
STATUS
EVALUATION WAS MADE UNDER THE PROJECT AGREEMENT CIS-03-95
WITH INTERNATIONAL SCIENCE AND TECHNOLOGY CENTER (MOSCOW).
FINANCING PARTY OF THE CENTER FOR THE PROJECT IS JAPAN.
EVALUATION WAS REQUESTED BY Y.KIKUCHI (JAERI, TOKAI)
DOCUMENTED IN INDC(BLR)-006, 1996.
MF=1 GENERAL INFORMATION
MT=451 COMMENTS AND DICTIONARY
MT=452 TOTAL NUMBER OF NEUTRONS PER FISSION
SUM OF MT=455 AND MT=456.
MT=455 DELAYED NEUTRON DATA
NUMBER OF DELAYED NEUTRONS AND
DECAY CONSTANTS FROM BRADY ET AL./1 /
MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION
MADLAND-NIX MODEL CALCULATIONS /2/ FITTED TO
THE MEASURED DATA OF KHOKHLOV ET AL. /3/ AND
FREHAUT ET AL. /4/. ABOVE EMISSIVE FISSION
THRESHOLD A SUPERPOSITION OF NEUTRON EMISSION
IN (N,XNF) REACTIONS /5/ AND PROMPT FISSION
NEUTRONS IS EMPLOYED.
MF=2 RESONANCE PARAMETERS
MT=151 RESONANCE PARAMETERS (MLBW)
RESOLVED RESONANCE REGION : 1.0E-5 - 250 EV
PARAMETERS FOR BREIT -WIGNER FORMULA ARE BASED UPON
THE TOTAL CROSS SECTION MEASUREMENTS OF BERRETH ET AL.
/6/ AND SIMPSON ET AL./7/, FISSION CROSS SECTION
MEASUREMENTS OF KNITTER ET AL./8/ AND SEEGER/9/.
THE LATTER BEING NORMALIZED TO GIVE =0.228mEV
THERMAL TOTAL BASED ON BERRETH ET AL./6/.
THERMAL FISSION BASED ON DATA OF HULET ET AL./10/,
BELANOVA ET AL./11/, ASGHAR AT AL./12/ AND WAGEMANS
ET AL./13/.
THERMAL CAPTURE BASED ON BUTLER ET AL./14/,
BAK ET AL./15/ AND FOLGER ET AL./16/.
CALCULATED THERMAL CROSS SECTIONS AND RESONANCE
INTEGRALS ARE:
2200 M/SEC RES.INTEG.
TOTAL 84.2330 b -
ELASTIC 7.4642 b -
FISSION 0.0638 b 7.436
CAPTURE 76.7050 b 1788.150
UNRESOLVED RESONANCE REGION : 0.25 - 42.3751 KEV.
ENERGY INDEPENDENT PARAMETERS:
R=9.11891 FM FROM OPTICAL MODEL CALCULATIONS
S1=2.176*10-4 FROM OPTICAL MODEL CALCULATIONS
S2=1.059*10-4 FROM OPTICAL MODEL CALCULATIONS
ENERGY DEPENDENT PARAMETERS:
S0 -DECREASES FROM .873-4 (0.15KEV) TO .834-4 (42.4KEV)
D - SPIN DEPENDENT, NORMALIZED TO =0.566 EV
WITH ACCOUNT OF LEVEL MISSING /17/
WF -SPIN DEPENDENT AS DEFINED BY THE TRANSITION STATE
SPECTRA AT INNER AND OUTER BARRIER HUMPS, NORMALIZED
TO =0.228 mEV TO FIT UNRESOLVED RESONANCE REGION
EXPERIMENTAL FISSION DATA /8,18/.
WG - FROM CASCADE MODEL WITH ACCOUNT OF FISSION AND
NEUTRON EMISSION COMPETITION, SPIN DEPENDENT. NORMA-
LIZED TO = 0.043 EV.( FITTS /18,19/).
MF=3 NEUTRON CROSS SECTIONS
MT=1,4,51-60,91,102. TOTAL, ELASTIC AND INELASTIC
SCATTERING, CAPTURE CROSS SECTION
TOTAL,DIRECT ELASTIC AND DIRECT INELASTIC FOR MT=51,
53,56 AND OPTICAL TRANSMISSION COEFFICIENTS FROM
COUPLED CHANNELS CALCULATIONS.
THE DEFORMED OPTICAL POTENTIAL USED:
VR=(46.04-0.3*E) MEV RR=1.26 FM AR=0.615 FM
WD=(3.50+0.4*E) MEV E < 10 MEV RD=1.24 FM
WD= 7.50 MEV E=> 10 MEV AD=0.5 FM
VSO=6.2 MEV RSO=1.12 FM ASO=0.47 FM B2=0.180 B4=0.086
FOUR LOWER LEVELS OF GROUND STATE ROTATIONAL BAND
ARE COUPLED.
CAPTURE,COMPOUND ELASTIC AND INELASTIC BY STATISTICAL
MODEL, SEE MT=18-21
ABOVE NEUTRON ENERGY 5 MEV CAPTURE IS ASSUMED TO BE
0.001 BARN AS PREDICTED BY DIRECT AND SEMI-DIRECT
CAPTURE CALCULATIONS
ADOPTED LEVEL SCHEME OF AM-243 FROM NUCLEAR DATA
SHEETS /20/
No ENERGY(MEV) SPIN-PARITY K
g.s. 0.0 5/2 - 5/2
1 0.0422 7/2 - 5/2
2 0.084 5/2 + 5/2
3 0.0964 9/2 - 5/2
4 0.1092 7/2 + 5/2
5 0.1435 9/2 + 5/2
6 0.1623 11/2 - 5/2
7 0.1893 11/2 + 5/2
8 0.238 13/2 - 5/2
9 0.244 13/2 + 5/2
10 0.266 3/2 - 5/2
OVERLAPPING LEVELS ARE ASSUMED ABOVE 0.267 MEV
LEVEL DENSITY PARAMETERS: SEE MT 18-21
MT=16,17. (N,2N) AND (N,3N) CROSS SECTION
FROM STATISTICAL MODEL CALCULATIONS /21/ WITH THE
ACCOUNT OF PRE-EQUILIBRIUM NEUTRON EMISSION:SEE MT=18-21
MT=18,19,20,21. FISSION CROSS SECTION IS CALCULATED WITHIN
STATISTICAL MODEL /22,23/, THE MEASURED DATA OF:
WISSHAK ET AL./18/, KNITTER ET AL. /8/,
FURSOV ET AL./24/ ARE FITTED.
THE FIRST CHANCE FISSION MT=19 IS CALCULATED WITH
THE CONTRIBUTION OF EMISSIVE FISSION TO TOTAL FISSION
CROSS SECTION ACCORDING TO /22,25/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
FOR MT=2,51,53,56 FROM COUPLED CHANNELS CALCULATIONS
WITH ADDED ISOTROPIC STATISTICAL CONTRIBUTION.
MT=16,17,18-21,52,54,55,57-60,91 - ISOTROPIC
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
ENERGY DISTRIBUTIONS FOR MT=16,17 WERE
CALCULATED BY STATISTICAL MODEL OF CASCADE NEUTRON
EMISSION TAKING INTO ACCOUNT THE HISTORY OF THE DECAY
WITH THE ALLOWANCE OF PRE-EQUILLIBRIUM EMISSION OF
THE FIRST NEUTRON /5/
ENERGY DISTRIBUTIONS FOR MT=18,19,20,21 WERE CALCULATED
BY MADLAND-NIX MODEL /2/ WITH ACCOUNT OF COMPETITION
BETWEEN MULTIPLE-CHANCE FISSION PROCESSES UP THROUGH
THIRD-CHANCE FISSION WITH THE ALLOWANCE OF PRE-EQUILIBRIUM
EMISSION OF THE FIRST NEUTRON /5,21/
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