96-Cm-246 MINSK BYEL EVAL-NOV95 V.M. Maslov et al.
INDC(BLR)-004/G DIST-MAR02 REV2-MAR00 20000328
----JENDL-3.3 MATERIAL 9643
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
83-03 New evaluation was made by Y.Kikuchi (JAERI) /Ki84/
89-03 Re-evaluation for JENDL-3.2 was made by T.Nakagawa /Na90/
00-02 JENDL-3.3 was compiled by T.Nakagawa
Evaluated data of Maslov et al. /Ma96/ were extensively
adopted.
***** Modified parts from JENDL-3.2 *******************
All data
*******************************************************
=================================================================
Description on modified parts from Maslov's evaluation.
=================================================================
MF=2 Resonance Rapameters
MT=151
The background cross section of fission was modified on the
basis of experimental data of Maguire et al. /Ma85/
Unresolved resonance parameters
The level spacing was modified to keep consistency with
that of L=0 and J=0.5. The neutron width was also modified
with the same factor of the level spacing. Interpolation
of cross sections was changed to 5 (log-log).
Calculated Thermal cross sections and Resonance integral
at .0253 eV (b) Res. Integ. (b)
Total 10.664 -
Elastic 9.208 -
Fission 0.144 10.4
Capture 1.311 115
MF=3 Neutron Cross Sections
MT=2 elastic
Calculated as Total - partial cross sections.
MT=18 Fission
Above the unresolved resonance region, the data were
determined on the basis of experimental data of Fursov et al.
/Fu97/.
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.
Other parts are the same as Maslov's evaluation.
References
Fu97) Fursov B.I. et al.: Int. Conf. Nuclear data for Sci. and
Technol., Trieste, Italy, 19-24 May 1997, Part 1, p488 (1997).
Ka99) Kawano T.: private communication (1999).
Ki84) Kikuchi Y.: JAERI-M 83-236 (1984).
Ma85) Maguire Jr. H.T. et al.: Nucl. Sci. Eng., 89, 293 (1985).
Ma96) Maslov V.M. et al.: INDC(BLR)-004/G (1996).
Na90) Nakagawa T.: JAERI-M 90-101 (1990).
========== Description given in Maslov's data ===================
96-Cm-246 MINSK BYEL EVAL-NOV 5
DIST-FEB96
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)
MF=1 GENERAL INFORMATION
MT=451 COMMENTS AND DICTIONARY
MT=452 NUMBER OF NEUTRONS PER FISSION
SUM OF MT=455 AND MT=456.
MT=455 DELAYED NEUTRON DATA
DECAY CONSTANTS FROM BRADY ET AL./1 /
NUMBER OF NEUTRONS PER FISSION FROM TUTTLE'S
SYSTEMATICS /2/.
MT=456 NUMBER OF NEUTRONS PER FISSION BASED ON
MADLAND-NIX MODEL CALCULATIONS /3/, ABOVE
EMISSIVE FISSION THRESHOLD A SUPERPOSITION OF
NEUTRON EMISSION IN (N,XNF) REACTIONS /4/ AND PROMPT
FISSION NEUTRONS
MF=2 RESONANCE PARAMETERS
MT=151 RESONANCE PARAMETERS (MLBW)
RESOLVED RESONANCE REGION : 1.0E-5 - 400 EV
PARAMETERS FOR BREIT-WIGNER FORMULA ARE BASED ON
THE DATA OF MOORE ET AL./5/ AND MAGUIRE ET AL./6/.,
REVISED BY DANON ET AL./7/
UNRESOLVED RESONANCE REGION : 0.4 - 43.0277 KEV.
ENERGY INDEPENDENT PARAMETERS:
R=9.0323 FM FROM OPTICAL MODEL CALCULATIONS
S1=2.769E-4 FROM OPTICAL MODEL CALCULATIONS
S2=1.023E-4 FROM OPTICAL MODEL CALCULATIONS
ENERGY DEPENDENT PARAMETERS:
S0 - DECREASES FROM 0.89E-4 (0.4KEV)TO 0.859E-4(43KEV)
D - SPIN DEPENDENT, NORMALIZED TO =17.5 EV
WITH ACCOUNT OF LEVEL MISSING /8/
WF -SPIN DEPENDENT AS DEFINED BY THE TRANSITION STATE
SPECTRA AT INNER AND OUTER BARRIER HUMPS,NORMALIZED
TO =1.33E-03 EV TO FIT UNRESOLVED RESONANCE
REGION EXPERIMENTAL FISSION DATA /6,7/.
WG - FROM CASCADE MODEL WITH ACCOUNT OF FISSION
COMPETITION,SPIN DEPENDENT. NORMALIZED TO =
0.0347 EV.
CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE
INTEGRALS.
2200 M/SEC RES.INTEG.
TOTAL 10.664 b -
ELASTIC 9.208 b -
FISSION 0.144 b 114.596
CAPTURE 1.311 b 10.281
MF=3 NEUTRON CROSS SECTIONS
MT=1,2,4,51-70,91,102. TOTAL, ELASTIC AND INELASTIC
SCATTERING, CAPTURE CROSS SECTION
TOTAL,DIRECT ELASTIC AND DIRECT INELASTIC FOR MT=51-
54 AND OPTICAL TRANSMISSION COEFFICIENTS ARE FROM
COUPLED CHANNELS CALCULATIONS.
THE DEFORMED OPTICAL POTENTIAL USED:
VR=46.33-0.3*E(MEV) RR=1.26 FM AR=0.615 FM
WD= 3.68+0.4*E(MEV) E < 10 MEV RD=1.24 FM
WD= 7.68 E > 10 MEV AD=0.5 FM
VSO=6.4 RSO=1.12 ASO=0.47 B2=0.203 B4=0.009
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 CM-246 FROM NUCLEAR DATA
SHEETS /9/ (19 LEVELS) PLUS 2 LEVELS ADDED/10/ FOR BAND
K,P=0+, PLUS 1 LEVEL ADDED FOR BAND K,P=1- ACCORDING
TO EJK=E(BH)+A(J(J+1)-K(K+1))
No ENERGY(MEV) SPIN-PARITY K
g.s. 0.0 0 + 0
1 0.04258 2 + 0
2 0.14201 4 + 0
3 0.29490 6 + 0
4 0.50040 8 + 0
5 0.78207 10 + 0 *
6 0.84167 2 - 2
7 0.87643 3 - 2
8 0.92331 4 - 2
9 0.98000 5 - 2
10 1.05170 6 - 2
11 1.07885 1 - 1
12 1.10485 2 - 1
13 1.10550 12 + 0 *
14 1.12427 2 + 2
15 1.12802 3 - 1
16 1.12940 7 - 2
17 1.16549 3 + 2
18 1.17474 0 + 0
19 1.17920 8 - 2
20 1.19580 4 - 1 *
21 1.21053 2 + 0
* - ADDED
OVERLAPPING LEVELS ARE ASSUMED ABOVE 1.22 MEV
LEVEL DENSITY PARAMETERS: SEE MT 18-21
MT=16,17. (N,2N) AND (N,3N) CROSS SECTION
FROM STATISTICAL MODEL CALCULATIONS /11/ WITH THE
ACCOUNT OF PRE-EQUILIBRIUM NEUTRON EMISSION:SEE MT=18-21
MT=18,19,20,21. FISSION CROSS SECTION
BASED ON DATA OF FOMUSHKIN ET AL./12/,MAGUIRE ET AL./6/,
REVISED BY DANON ET AL./7/.
THE FIRST CHANCE FISSION MT=19 IS CALCULATED WITH
THE LEVEL DENSITY AND FISSION BARRIER PARAMETERS:
TRANSITION SPECTRA BAND HEADS OF 247-CM
INNER SADDLE OUTER SADDLE
K,P EKP K,P EKP
1/2+ 0.0 1/2+ 0.0
5/2+ 0.08 1/2- 0.0
1/2- 0.05 3/2+ 0.08
3/2- 0.0 3/2- 0.08
5/2+ 0.0
5/2- 0.0
FISSION BARRIER PARAMETERS OF 247-CM
BARRIER BARRIER HEIGHT, MEV CURVATURE, MEV
INNER 6.17 0.7
OUTER 5.40 0.6
THE CONTRIBUTION OF EMISSIVE FISSION TO THE TOTAL FISSION
CROSS SECTION IS CALCULATED ACCORDING TO /11,13/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
FOR MT=2,51-54 FROM COUPLED CHANNELS CALCULATIONS
WITH ADDED ISOTROPIC STATISTICAL CONTRIBUTION.
MT=16,17,18-21,55-70,91 ISOTROPIC
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
ENERGY DISTRIBUTIONS FOR MT=16,17,18,19,20,21 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 /4/
REFERENCES
1. Brady M.C.,Wright R.Q., England T.R.,Report ORNL/CSD/TM-
226(1991), IAEA-NDS-102,1992
2. Tuttle R.J. Proc. Consultants Meeting on Delayed Neutron
Properties, 1979, Vienna, INDC(NDS)-107/G, p.29.
3. Madland D.G., Nix J.R., Nucl. Sci. Eng., 81, 213, (1982).
4. Maslov V.M., Porodzinskij Yu.V.,Sukhovitskij E.Sh., Proc.
Int. Conf. on Neutron Physics, 14-18 Sept., Kiev, USSR,
v.1, p.413, 1988.
5. Moore M.S., Keyworth G.A.: Phys. Rev. C, v3 (1971) 1656.
6. Maguire Jr.H.T.,Stopa C.R.S.,Block R.C.et al.:Nucl.Sci.,
Eng.89(1985) 293.
7. Danon Y., Slovacek R.E., Block R.C. et al.: Nucl.Sci.Eng.,
109 (1991) 341.
8. Porodzinskij Yu.V., Sukhovitskij E.Sh., Nuclear Constants, 4,
p.27, 1987 (in Russian)
9. Ellis-Akovali Y.A., Nucl. Data Sheets, 33, 119, 1981
10. Porodzinskij Yu.V., Sukhovitskij E.Sh., Sov. J. Nucl. Phys.53,
p.64, 1991
11. Ignatjuk A.V., Maslov V.M., Pashchenko A.B. Sov. J. Nucl.
Phys. 47, 224 (1988).
12. Fomushkin E.F., G.F. Novoselov, Vinigradov Yu.I.,Gavrilov G.F.
et al., Sov. J.Nucl. Phys. 36, 338 (1980).
13. Maslov V.M. Ann. Nucl. Energy, 20, 163, 1993.