96-Cm-243 MINSK BYEL EVAL-NOV95 V.M. Maslov et al.
INDC(BLR)-002/G DIST-MAR02 REV2-MAR00 20000329
----JENDL-3.3 MATERIAL 9634
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
81-03 Evaluation for JENDL-2 was made by T.Nakagawa and S.Igarasi
/Na81/
89-03 Re-evaluation for JENDL-3 was made by T.Nakagawa /Na90/
00-02 JENDL-3.3 was compiled by T.Nakagawa
Evaluated data of Maslov et al. /Ma95/ 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
Resolved resonance parameters
Flag was changed to MLBW.
Unresolved resonance parameters
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 of the level spacing. Interpolation
of cross sections was changed to 5 (log-log).
Calculated Thermal cross sections and Resonance integral
at 0.0253 eV (b) Res. Integ. (b)
Total 752.74 -
Elastic 8.875 -
Fission 613.33 1540
Capture 130.53 212
MF=3 Neutron Cross Sections
MT=2 elastic
Calculated as Total - partial cross sections.
MT=18 Fission
Above the unresolved resonance region, Maslov's evaluation was
adopted up to 100 keV. Above 800 keV, BROND-3 data /Ig97/ were
adopted because the resent experimental data of Fursov et al.
/Fu97/ were reproduced well. Between 100 and 800 keV,
determined by eye-guiding.
NOTE: The data of MT's=19, 20 and 21 calculated by Maslov et
al. /Ma95/ 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).
Ig97) Ignatyuk A.V. et al.: ISTC 304-95 (1997). Numerical data
were from Ignatyuk (1999).
Ka99) Kawano T.: private communication (1999).
Ma95) Maslov V.M. et al.: INDC(BLR)-002/L (1995).
Na81) Nakagawa T. and Igarasi S.: JAERI-M 9601 (1981).
Na90) Nakagawa T.: JAERI-M 90-101 (1990).
========== Description given in Maslov's data ===================
96-Cm-243 MINSK BYEL EVAL-JUL95
DIST-AUG95
V.M. MASLOV, E.Sh. SUKHOVITSKIJ,
Yu.V. PORODZINSKIJ, A.B. KLEPATSKIJ,
G.B. MOROGOVSKIJ
RADIATION PHYSICS AND CHEMISTRY PROBLEMS INSTITUTE, MINSK-SOSNY
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)
PROJECT MANAGER V.M. MASLOV (MINSK)
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
ESTIMATED FROM THE SYSTEMATICS BY TUTTLE /1/.
MT=456 NUMBER OF NEUTRONS PER FISSION
BASED ON THE EXPERIMENTAL DATA AT THERMAL ENERGY BY
JAFFEY AND LERNER /2/, ZHURAVLEV ET AL. /3/
AND ON THE MADLAND-NIX MODEL CALCULATION /4/, ABOVE
EMISSIVE FISSION THRESHOLD A SUPERPOSITION OF
NEUTRON EMISSION IN (N,XNF) REACTIONS /5/ AND PROMPT
FISSION NEUTRONS
MF=2 RESONANCE PARAMETERS
MT=151 RESONANCE PARAMETERS (SLBW)
RESOLVED RESONANCE REGION : 1.0E-5 - 100 EV
PARAMETERS FOR BREIGT-WIGNER FORMULA ARE BASED ON
THE WORKS OF ANUFRIEV ET AL. /6/ AND SILBERT /7/.
UNRESOLVED RESONANCE REGION : 0.1 - 42.1743 KEV.
ENERGY INDEPENDENT PARAMETERS:
R=9.4757 FM FROM OPTICAL MODEL CALCULATIONS
S1=2.12E-4 FROM OPTICAL MODEL CALCULATIONS
S2=1.458-4 EQUEL S0 WITH ACCOUNT OF MISSING
ENERGY DEPENDENT PARAMETERS:
S0 - OBTAINED BY FITTING FISSION DATA OF REF./7/
D - SPIN DEPENDENT, NORMALIZED TO =0.679 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 =0.355 EV FROM RESOLVED RESONANCE REGION.
WG - FROM CASCADE MODEL WITH THE ACCOUNT OF FISSION
COMPETITION,SPIN DEPENDENT. NORMALIZED TO =
0.0402 EV.
CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE
INTEGRALS.
2200 M/SEC RES.INTEG.
TOTAL 752.419 b -
ELASTIC 8.577 b -
FISSION 613.319 b 1530.99
CAPTURE 130.523 b 211.66
MF=3 NEUTRON CROSS SECTIONS
MT=1,4,51-74,91,102. TOTAL, ELASTIC AND INELASTIC
SCATTERING, CAPTURE CROSS SECTION
TOTAL,DIRECT ELASTIC AND DIRECT INELASTIC FOR MT=51,
53,57,60,64 AND OPTICAL TRANSMISSION COEFFICIENTS FROM
COUPLED CHANNELS CALCULATIONS.
THE DEFORMED OPTICAL POTENTIAL USED:
VR=46.49-0.3*E(MEV) RR=1.26 FM AR=0.615 FM
WD= 3.77+0.4*E(MEV) E < 10 MEV RD=1.24 FM
WD= 7.77 E => 10 MEV AD=0.5 FM
VSO=6.4 RSO=1.12 ASO=0.47 B2=0.233 B4=0.067
CAPTURE,COMPAUND ELASTIC AND INELACTIC BY STATISTICAL
MODEL, SEE MT=18-21
ABOVE NEUTRON ENERGY 5 MEV CAPTURE IS ASUMED TO BE
0.001 BARN AS PREDICTED BY DIRECT AND SEMY-DIRECT
CAPTURE CALCULATIONS
ADOPTED LEVEL SCHEME OF CM-243 FROM NUCLEAR DATA
SHEETS /9/ (11 LEVELS) PLUS 14 LEVELS ADDED FOR BANDS
K,P=1/2+, 3/2+, 5/2-, 5/2+ ACCORDING TO
SYSTEMATICS FOR U-235 AND PU-239
No ENERGY(MEV) SPIN-PARITY K
g.s. 0.0 5/2 + 5/2
1 0.042 7/2 + 5/2
2 0.0874 1/2 + 1/2
3 0.0939 9/2 + 5/2
4 0.0940 3/2 + 1/2
5 0.133 7/2 + 7/2
6 0.140 5/2 + 1/2 *
7 0.153 11/2 + 5/2
8 0.158 7/2 + 1/2 *
9 0.164 9/2 + 7/2
10 0.219 13/2 + 5/2
11 0.228 11/2 + 7/2
12 0.260 9/2 + 1/2
13 0.280 11/2 + 1/2 *
14 0.300 15/2 + 5/2 *
15 0.305 5/2 - 5/2 *
16 0.310 3/2 + 3/2 *
17 0.311 13/2 + 7/2 *
18 0.320 7/2 - 5/2 *
19 0.340 5/2 + 3/2 *
20 0.354 9/2 - 5/2 *
21 0.380 13/2 + 1/2 *
22 0.390 15/2 + 7/2 *
23 0.395 11/2 - 5/2 *
24 0.400 17/2 + 5/2 *
* - ADDED
OVERLAPPING LEVELS ARE ASSUMED ABOVE 0.4 MEV
LEVEL DENSITY PERAMETERS: SEE MT 18-21
MT=16,17. (N,2N) AND (N,3N) CROSS SECTION
FROM STATISTICAL MODEL CALCULATIONS /10/ WITH THE
ACCOUNT OF PRE-EQUILIBRIUM NEUTRON EMISSION:SEE MT=18-21
MT=18,19,20,21. FISSION CROSS SECTION
THE FIRST CHANCE FISSION MT=19 WAS CALCULATED WITH
THE LEVEL DENSITY AND FISSION BARRIER PARAMETERS:
TRANSITION SPECTRA BAND HEADS OF 244-CM
INNER SADDLE OUTER SADDLE
K,P EKP K,P EKP
0 + 0.0 0 + 0.0
2 + 0.1 2 + 0.3
0 - 0.4 0 - 0.0
1 - 0.4 1 - 0.1
2 + 0.3 2 + 0.3
2 - 0.4 2 - 0.1
0 + 0.8 0 + 0.8
0 + 0.8 0 + 0.8
FISSION BARRIER PARAMETERS OF 244-CM
BARRIER BARRIER HEIGHT, MEV CURVATURE, MEV
INNER 6.43 0.9
OUTER 5.10 0.6
THE CONTRIBUTION OF EMISSIVE FISSION TO THE TOTAL FISSION
CROSS SECTION IS CALCULATED ACCORDING TO /11/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
FOR MT=2,51,53,57 FROM COUPLED CHANNELS CALCULATIONS
WITH ADDED ISOTROPIC STATISTICAL CONTRIBUTION.
MT=16,17,18,52,54-56,58-74,91,16 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 /5/
REFERENCES
1. Tuttle R.J. Proc. Consultants Meeting on Delayed Neutron
Properties, 1979, Vienna, INDC(NDS)-107/G, p.29.
2. Jaffey A.H., Lerner J.L., Nucl. Phys. A, 145, 1 (1870).
3. Zhuravlev K.D., Zamyatnin Yu.S., Kroshkin N.I., Neutron
Physics, Proc. of 2nd Conf. on Neutron Physics, v.4, 57
(1975).
4. Madland D.G., Nix J.R., Nucl. Sci. Eng., 81, 213, (1982).
5. 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.
6. V.A. Anufriev, S.I. Babich, N.G. Kochergin, V.M. Lebedev,
S.N. Nikolskij, V.N. Nefedov, V.M. Nikolaev, V.A. Poruchikov,
A.A. Elesin: Sov. Atomic Energy, 51 (1982) 736
7. M.G. Silbert: Fission Cross Section of 243-Cm from
the Underground Nuclear Explosion, Physics-8,
LA-6239-MS (1976).
8. Porodzinskij Yu.V., Sukhovitskij E.Sh., Nuclear Constants, 4,
p.27, 1987 (in Russian)
9. Ellis-Akovali Y.A., Nucl. Data Sheets, 44, 407
(1985) 16. Fomushkin E.F., G.F. Novoselov, Y.I. Vinogradov
et al., Atomnaya Energiya, 69, 258 (1990).
10. Ignatjuk A.V., Maslov V.M., Pashchenko A.B. Sov. J. Nucl.
Phys. 47, 224 (1988).
11. Maslov V.M. Ann. Nucl. Energy, 20, 163, 1993.