96-Cm-245
96-Cm-245 MINSK,BYEL EVAL-NOV95 V.M. Maslov et al.
INDC(BLR)-003/L DIST-MAR02 REV4-APR00 20000420
----JENDL-3.3 MATERIAL 9640
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
78-03 Evaluation was made by Igarasi and T.Nakagawa /Ig78/
89-03 Re-evaluation for JENDL-3.2 was made by T.Nakagawa /Na90/
92-09 JENDL-3.2 was compiled by T.Nakagawa (NDC/JAERI)
00-04 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
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=3.0. 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 .0253 eV (b) Res. Integ. (b)
Total 2512.5 -
Elastic 10.88 -
Fission 2142.4 804
Capture 359.2 106
MF=3 Neutron Cross Sections
MT=2 elastic
Calculated as Total - partial cross sections.
MT=18 Fission
Above the unresolved resonance region, the data of JENDL-3.2
were adopted up to 7 MeV. Above this energy the evaluated data
of Maslov et al. /Ma96/ were adopted after multipling a factor
so as to reproduce the experimental data of Fursov et al.
/Fu97/ at 14.9 MeV.
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
Summation calculation by Brady and England /Br89/ 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).
Fu97) Fursov B.I. et al.: Int. Conf. Nuclear data for Sci. and
Technol., Trieste, Italy, 19-24 May 1997, Part 1, p488 (1997).
Ig78) Igarasi S. and Nakagawa T.: JAERI-M 7733 (1978).
Ka99) Kawano T.: private communication (1999).
Ma96) Maslov V.M. et al.: INDC(BLR)-003/L (1996).
Na90) Nakagawa T.: JAERI-M 90-101 (1990).
========== Description given in Maslov's data ===================
96-Cm-245 MINSK BYEL EVAL-NOV 5
DIST-NOV95
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 /AND TUTTLE'S
SYSTEMATICS /2/.
MT=456 NUMBER OF NEUTRONS PER FISSION
BASED ON THE EXPERIMENTAL DATA OF KHOKHLOV ET AL. /3/
AND MADLAND-NIX MODEL CALCULATIONS /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 BREIT -WIGNER FORMULA ARE BASED ON
THE DATA OF MOORE ET AL. /6/ AND BROWNE ET AL./7/.
UNRESOLVED RESONANCE REGION : 0.1 - 54.9553 KEV.
ENERGY INDEPENDENT PARAMETERS:
R=9.52044 FM FROM OPTICAL MODEL CALCULATIONS
S1=2.10E-4 FROM OPTICAL MODEL CALCULATIONS
S2=1.256-4 EQUALS S0 WITH ACCOUNT OF MISSING
ENERGY DEPENDENT PARAMETERS:
S0 - DECREASES FROM 1.256-4 (0.1KEV)TO 1.172-4 (55KEV)
D - SPIN DEPENDENT, NORMALIZED TO =0.698 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 =0.345 EV TO FIT UNRESOLVED RESONANCE REGION
EXPERIMENTAL FISSION DATA /6,9,10/.
WG - FROM CASCADE MODEL WITH ACCOUNT OF FISSION
COMPETITION,SPIN DEPENDENT. NORMALIZED TO =
0.0378 EV.
CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE
INTEGRALS.
2200 M/SEC RES.INTEG.
TOTAL 2512.500 b -
ELASTIC 10.973 b -
FISSION 2142.382 b 793.927
CAPTURE 359.145 b 105.404
MF=3 NEUTRON CROSS SECTIONS
MT=1,4,51-67,91,102. TOTAL, ELASTIC AND INELASTIC
SCATTERING, CAPTURE CROSS SECTION
TOTAL,DIRECT ELASTIC AND DIRECT INELASTIC FOR MT=51,
52,53,55,61 AND OPTICAL TRANSMISSION COEFFICIENTS FROM
COUPLED CHANNELS CALCULATIONS.
THE DEFORMED OPTICAL POTENTIAL USED:
VR=46.38-0.3*E(MEV) RR=1.26 FM AR=0.615 FM
WD= 3.71+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=0.076
CAPTURE,COMPOUND ELASTIC AND INELASTIC BY STATISTICAL
MODEL, SEE MT=18-21
ABOVE NEUTRON ENERGY 5 MEV CAPTURE IS ASSUMED TO BE
0.0001 BARN AS PREDICTED BY DIRECT AND SEMI-DIRECT
CAPTURE CALCULATIONS
ADOPTED LEVEL SCHEME OF CM-245 FROM NUCLEAR DATA
SHEETS /11/ (15 LEVELS) PLUS 2 LEVELS ADDED FOR BAND
K,P=7/2+ ACCORDING TO EJ=A(J(J+1)-K(K+1))
No ENERGY(MEV) SPIN-PARITY K
g.s. 0.0 7/2 + 7/2
1 0.05473 9/2 + 7/2
2 0.1214 11/2 + 7/2
3 0.1971 13/2 + 7/2
4 0.25285 5/2 + 5/2
5 0.2923 15/2 + 7/2 *
6 0.29584 7/2 + 5/2
7 0.3505 9/2 + 5/2
8 0.35595 1/2 + 1/2
9 0.3615 3/2 + 1/2
10 0.38795 9/2 - 9/2
11 0.3957 17/2 + 7/2 *
12 0.417 11/2 + 5/2
13 0.4188 5/2 + 1/2
14 0.431 7/2 + 1/2
15 0.4428 11/2 - 9/2
16 0.4980 13/2 + 5/2
17 0.5087 13/2 - 9/2
* - ADDED
OVERLAPPING LEVELS ARE ASSUMED ABOVE 0.50874 MEV
LEVEL DENSITY PARAMETERS: SEE MT 18-21
MT=16,17. (N,2N) AND (N,3N) CROSS SECTION
FROM STATISTICAL MODEL CALCULATIONS /12/ 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/, WHITE ET AL./10/
AND FURSOV ET AL./13/.
THE FIRST CHANCE FISSION MT=19 IS CALCULATED WITH
THE LEVEL DENSITY AND FISSION BARRIER PARAMETERS:
TRANSITION SPECTRA BAND HEADS OF 246-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 + 0.5 2 + 0.5
2 - 0.4 2 - 0.1
0 + 0.8 0 + 0.8
0 + 0.8 0 + 0.8
FISSION BARRIER PARAMETERS OF 246-CM
BARRIER BARRIER HEIGHT, MEV CURVATURE, MEV
INNER 6.00 0.9
OUTER 4.80 0.6
THE CONTRIBUTION OF EMISSIVE FISSION TO THE TOTAL FISSION
CROSS SECTION IS CALCULATED ACCORDING TO /14,15/.
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. Brady M.C.and England T.R., Nucl.Sci.Eng., 145,129 (1989).
2. Tuttle R.J. Proc. Consultants Meeting on Delayed Neutron
Properties, 1979, Vienna, INDC(NDS)-107/G, p.29.
3. Khokhlov Yu.A., Ivanin I.A., In'kov V.I., et al., Proc of
Int. Conf. on Nucl. Data for Sci. and Tech., 9-13 May,
Gatlinburg, v.1, p.272, 1994.
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. M.S. Moore, G.A. Keyworth: Phys. Rev. C, v3 (1971) 1656.
7. J.C. Browne, R.W. Benjamin, D.G. Karraker: Nucl. Sci. Eng.,
65(1978) 166.
8. Porodzinskij Yu.V., Sukhovitskij E.Sh., Nuclear Constants, 4,
p.27, 1987 (in Russian)
9. Gerasimov V.F., Danitchev V.V., Dementiev V.N., Proc of Int.
Conf.on Neutron Physics., 14-18 Sept., Kiev, USSR, v.3,
p.84, 1987
10. WhitE R.M., BROWNE J.C., Proc of Int. Conf. on Nucl. Data for
Sci. and Tech., Antwerpen, p.218, 1983
11. Ellis-Akovali Y.A., Nucl. Data Sheets, 33, 119, 1981
12. Fomushkin E.F., G.F. Novoselov, Y.I. Vinogradov
et al., Atomnaya Energiya, 69, 258 (1990).
13. FURSOV B.I., SAMYLIN B.F., SMIRENKIN G.N. ET AL. Nuclear Data
for Science and Technology, Gatlinburg, 1994, p.269, ANS.
14 Ignatjuk A.V., Maslov V.M., Pashchenko A.B. Sov. J. Nucl.
Phys. 47, 224 (1988).
15. Maslov V.M. Ann. Nucl. Energy, 20, 163, 1993.
========== Description given in Maslov's data (end) =============