94-Pu-238
95-Pu-238 MINSK BYEL EVAL-MAY97 V.M.Maslov et al.
INDC(BLR)-009/G DIST-MAR02 REV3-APR00 20000420
----JENDL-3.3 MATERIAL 9434
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
79-03 New evaluation was made by T.Kawakita (PNC).
89-03 Re-evaluation was made by T.Kawakita (MAPI) and
T.Nakagawa (JAERI).
94-06 JENDL-3.2
Nu-p, nu-d and nu-total were modified.
Compiled by T.Nakagawa (NDC/JAERI).
00-04 Compilation for JENDL-3.3 was made by T.Nakagawa
Evaluated data of Maslov et al. /Ma97/ were extensively
adopted.
***** Modified parts from JENDL-3.2 *******************
All data
*******************************************************
=================================================================
Modified parts from Maslov's evaluation.
=================================================================
MF=2 Resonance Rapameters
MT=151
Resolved resonance parameters (MLBW, 1.0E-5 - 500 eV)
Taken from JENDL-3.2.
**** Comment to JENDL-3.2 *****
ENERGY RANGE IS FROM 1.0E-5 EV TO 500 EV. PARAMETERS WERE
TAKEN FROM THE FOLLOWING EXPERIMENTAL DATA.
49 RESONANCES ABOVE 10 EV : SILBERT /Si73/
4 RESONANCES BELOW 10 EV : YOUNG /Yo67/
THE PARAMETERS OF TWO NEGATIVE AND 2.9-EV RESONANCES WERE
ADJUSTED TO THE THERMAL CROSS SECTIONS/Mu84/
Unresolved resonance parameters (500 eV - 44.2668 keV)
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).
Background cross section was given to MT=18 to connect the
fission cross section above the unresolved resonance
region and cross sections calculated from the unresolved
resonance parameters.
Calculated Thermal cross sections and Resonance integral
at .0253 eV (b) Res. Integ. (b)
Total 586.7 -
Elastic 28.6 -
Fission 17.9 32.4
Capture 540.3 152
MF=3 Neutron Cross Sections
MT=2 Elastic scattering
Calculated as Total - Sum of partial cross sections.
MT=18 Fission
The fission cross section was adopted from JENDL-3.2.
***** comment to JENDL-3.2 (MT=18) *****
EVALUATED MAINLY ON THE BASIS OF DATA MEASURED BY
BUDTZ-JORGENSEN/Bu83/ OTHER EXPERIMENTS /Si73, Ba67, Fo67,
Er68, Dr70, Er70, Fo70, Sh72, Al88/ WERE ALSO TAKEN INTO
CONSIDERATION.
****************************************
NOTE: The data of MT's=19, 20 and 21 calculated by Maslov et
al. /Ma97/ 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 Delayed Neutron Spectra
Results of summation calculation made by Brady and England
/Br89/ were adopted.
=================================================================
Other parts are the same as Maslov's evaluation.
=================================================================
REFERENCES
Al88) Alam B. et al.: Nucl. Sci. Eng., 99, 267 (1988).
Ba67) Barton D.M. and Koonty P.G.: Phys. Rev., 162, 1070 (1967).
Br89) Brady M.C. and England T.R.: Nucl. Sci. Eng., 103, 129
(1989).
Bu83) Budtz-Jorgensen C. et al.: 1982 Antwerp, 206 (1983).
Dr70) Drake D.M. et al.: LA-4420, p.101 (1970).
Er68) Ermagambetov S.B. and Shirenkin G.N.: Sov. J. Nucl. Phys.,
25, 1364 (1968).
Er70) Ermagambetov S.B. et al.: Sov. J. Nucl. Energy,29, 1190
(1970).
Fo67) Fomushkin E.F. et al.: Sov. J. Nucl. Phys., 5, 689 (1967).
Fo70) Fomushkin E.F. et al.: Sov. J. Nucl. Phys., 10, 529 (1970).
Ka99) Kawano T.: private communication (1999).
Ma97) Maslov V.M. et al.: INDC(BLR)-009/G (1997).
Mu84) Mughabghab S.F.: "Neutron Cross Sections, Vol. 1, Part B",
Academic Press (1984).
Sh72) Shpak D.L. et al.: JETP Letters, 15, 228 (1972).
Si73) Silbert M.G. et al.: Nucl. Sci. Eng., 52, 176 (1973).
Yo67) Young T.E. et al.: Nucl. Sci. Eng., 30, 355 (1967).
========== Description given in Maslov's data ===================
94-Pu-238 MINSK BYEL EVAL-MAY97
DIST-JULY97
V.M. MASLOV, E.Sh. SUKHOVITSKIJ,
Yu.V. PORODZINSKIJ, 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 ISTC FOR THE PROJECT IS JAPAN.
EVALUATION WAS REQUESTED BY JNDC (JAERI, TOKAI)
DOCUMENTED IN INDC(BLR)-009, 1997.
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 TUTTLE /1/ AND BRADY ET AL./2/
MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION
ABOVE EMISSIVE FISSION THRESHOLD IS A
SUPERPOSITION OF NEUTRON EMISSION
IN (N,XNF) REACTIONS AND PROMPT FISSION
NEUTRONS.
MF=2 RESONANCE PARAMETERS
MT=151 RESONANCE PARAMETERS (MLBW)
RESOLVED RESONANCE REGION : 1.0E-5 - 500 EV
PARAMETERS FOR BREIT-WIGNER FORMULA ARE BASED UPON
THE TOTAL CROSS SECTION MEASUREMENT BY YOUNG /3/;
THE FISSION CROSS SECTION MEASUREMENTS OF SILBERT
/4/, STUBBINS /5/, BUDTZ-JOERGENSEN /6/, ALAM /7/,
GERASIMOV /8/, DRAKE /9/; CAPTURE CROSS
SECTION MEASUREMENT SILBERT /10/.
CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE
INTEGRALS ARE:
2200 M/SEC RES.INTEG.
TOTAL 579.544 b -
ELASTIC 21.965 b -
FISSION 16.601 b 28.4497
CAPTURE 540.978 b 141.765
UNRESOLVED RESONANCE REGION :
ENERGY INDEPENDENT PARAMETERS:
R=9.238 FM FROM OPTICAL MODEL CALCULATIONS
S1=2.399*10-4 FROM OPTICAL MODEL CALCULATIONS
S2=1.242*10-4 FROM OPTICAL MODEL CALCULATIONS
ENERGY DEPENDENT PARAMETERS:
S0-DECREASES FROM 1.036-4(0.50KEV) TO 0.968-4(44.27KEV)
FISSION WIDTH FLUCTUATES TO FIT FISSION CROSS SECTION.
D - SPIN DEPENDENT, NORMALIZED TO =8.301 EV
WITH ACCOUNT OF LEVEL MISSING /11/.
WF -SPIN DEPENDENT AS DEFINED BY THE TRANSITION STATE
SPECTRA AT INNER AND OUTER BARRIER HUMPS, NORMALIZED
TO = 34 mEV TO FIT UNRESOLVED RESONANCE REGION
EXPERIMENTAL FISSION DATA.
WG - FROM CASCADE MODEL WITH ACCOUNT OF FISSION AND
NEUTRON EMISSION COMPETITION, SPIN DEPENDENT. NORMA-
LIZED TO = 0.03485 EV.
MF=3 NEUTRON CROSS SECTIONS
MT=1,4,51-69,91,102. TOTAL, ELASTIC AND INELASTIC
SCATTERING, CAPTURE CROSS SECTION
TOTAL,DIRECT ELASTIC AND DIRECT INELASTIC FOR MT=51,
52,53 AND OPTICAL TRANSMISSION COEFFICIENTS FROM
COUPLED CHANNELS CALCULATIONS.
THE DEFORMED OPTICAL POTENTIAL USED:
VR=(46.26-0.3*E) MEV RR=1.26 FM AR=0.615 FM
WD=(3.63+0.4*E) MEV E < 10 MEV RD=1.24 FM
WD= 7.63 MEV E=> 10 MEV AD=0.5 FM
VSO=6.2 MEV RSO=1.12 FM ASO=0.47 FM B2=0.197 B4=0.061
FOUR LEVELS OF ROTATIONAL GROUND STATE 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
CONSTANT.
ADOPTED LEVEL SCHEME OF PU-238 FROM NUCLEAR DATA
SHEETS /12/.
No ENERGY(MEV) SPIN-PARITY K
g.s. 0.0 0 + ?
1 0.04408 2 + ?
2 0.14598 4 + ?
3 0.30340 6 + ?
4 0.51347 8 + ?
5 0.60518 1 - 5
6 0.66143 3 - 6
7 0.76320 5 - 0
8 0.77280 10 + 0
9 0.94150 0 + 5
10 0.96277 1 -
11 0.96810 2 - 6
12 0.98310 2 + 1
13 0.98546 2 - 1
14 1.02855 2 + 1
15 1.06995 3 + 3
16 1.07850 12 + 0
17 1.08257 4 - 0
18 1.12580 4 +
19 1.13400 0 + 1
OVERLAPPING LEVELS ARE ASSUMED ABOVE 1.14 MEV
LEVEL DENSITY PARAMETERS: SEE MT 18-21
MT=16,17. (N,2N) AND (N,3N) CROSS SECTION
FROM STATISTICAL MODEL CALCULATIONS /13/ 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 /14,15,16/ THE MEASURED DATA BY:
BUDTZ-JORGENSEN /6/, ALAM ET AL. /7/,
ERMAGAMBETOV ET AL./17,18/, FOMUSHKIN ET AL./19,20/,
ARE FITTED.
THE FIRST CHANCE FISSION MT=19 IS CALCULATED WITH
THE CONTRIBUTION OF EMISSIVE FISSION TO TOTAL FISSION
CROSS SECTION ACCORDING TO /14/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
FOR MT=2, 55, 59 FROM COUPLED CHANNELS CALCULATIONS
WITH ADDED ISOTROPIC STATISTICAL CONTRIBUTION.
MT=16,17,18-21,54-69,91 - 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 /21/
ENERGY DISTRIBUTIONS FOR MT=18,19,20,21 WERE CALCULATED
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 /21 /.
REFERENCES
1. Tuttle R.J. Proc. Consultants Meeting on Delayed Neutron
Properties, 1979, Vienna, INDC(NDS)-107/G, p.29.
2. Brady M..C., Wright R.Q., England T.R., Report ORNL/CSD/TM-
226 (1991), IAEA-NDS-1)2, 1992.
3. Young T.E., Simpson F.B.,Berreth J.R., Coops M.S. Nucl. Sci.
Engng. 30, 355 (1967).
4. Silbert M.G., Moat A., Young T.E. Nucl.Sci.Eng. 52, 176 (1973)
5. Stubbins W.F., Bowman C.D., Auchampaugh G.F., Coops M.F.
Phys. Rev. 154, 1111 (1967).
6. Budtz-Jorgensen C., Knitter H.H. and Smith D.L. Proc.Int.
Conf. Nuclear Data for Science and Technology, Antwerpen,
Belgium, September 6-10, 1982, p. 206, ? del Publishing Co.
Boston (1983).
7. Alam B., Block R.C., Slovacek R.E., Hoff R.W. Nucl. Sci. Eng.
99, 267 (1988).
8. Gerasimov V.F., Sov.J.Nucl.Phys., 4, 706 (1967).
9. Drake D.M. et al. LA-4420, p.101, 1970.
10. Silbert M.G., Berreth J.R. Nucl. Sci. Eng., 52, 187 (1973).
11. Porodzinskij Yu.V., Sukhovitskij E.Sh. and Maslov B.M. Int.
Conf. Nuclear Data for Science and Technology, Trieste,
Italy, May 19-24, 1997, to be published.
12. ENSDF, 1995.
13. Ignatjuk A.V., Maslov V.M., Pashchenko A.B. Sov.J.Nucl.Phys.
47, 224 (1988).
14. Ignatjuk A.V., Maslov V.M., Proc.Int.Symp.Nuclear Data
Evaluation Methodology, Brookhaven, USA, October 12-16,
p.440, World Scientific, 1993.
15. Maslov B.M., Kikuchi Y. JAERI-Research 96-030, June, 1996.
16. Maslov B.M. Int.Conf.Nuclear Data for Science And Technology,
Trieste, Italy, May 19-24, 1997, to be published.
17. Ermagambetov S.V., Smirenkin G.N. Sov.At.Energy, 25, 1364
(1968).
18. Ermagambetov S.V., Smirenkin G.N. JETP Letters, 9, 309 (1969).
19. Fomushkin E.F., Gutnikova E.K. Sov.J.Nucl.Phys., 10, 529
(1970).
20. Fomushkin E.F., Gutnikova E.K., Zamyatnin Yu.S. et al.
Sov.J.Nucl.Phys., 5, 966 (1967).
21. Maslov B.M, Porodzinskij Yu.V., Sukhovitskij E.Sh., Proc.
Int.Conf. on Neutron Physics, 14-18 Sept., Kiev, USSR, v.1,
p.413, 1988.