92-U -233
92-U -233 SAEI+ Eval-Mar00 T.Mutsunobu, T.Kawano
DIST-MAR02 Rev4-May00 20020214
----JENDL-3.3 MATERIAL 9222
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
82-06 Evaluation for JENDL-2 was made by N. Asano (SAEI),
H. Matsunobu (SAEI) and Y.Kikuchi(JAERI).
87-03 Re-evaluation for JENDL-3 was made by H.Matsunobu (SAEI)
Main part of revision was the cross sections above 10 keV
and angular and energy distributions of neutrons.
Data were compiled by T. Nakagawa (JAERI).
94-04 JENDL-3.2.
Resonance parameters reevaluated by H.Derrien (JAERI)/1/
Cross sections reevaluated by H.Matsunobu(SAEI)
Fission spectrum reevaluated by T.Ohsawa(Kinki univ.)
Compiled by T.Nakagawa (NDC/JAERI)
***** Modified parts for JENDL-3.2 ********************
(2,151); New analysis with SAMMY
MF=3 ; all data except fission cross section below 6.75
MeV and total cross section
MF=4 ; for inelastic scattering
(5,18)
***********************************************************
00-02 JENDL-3.3. Evaluation was made by H. Matsunobu (SAEI)
and T.Kawano(Kyushu Univ.) and compiled by O.Iwamoto
(NDC/JAERI).
***** Modified parts for JENDL-3.3 ********************
(1,452), (1,455), (1,456)
(2,151) unresolved resonance region
(3,2), (3,16), (3,17), (3,18), (3,102)
(5,16), (5,17), (5,91), (5,455)
***********************************************************
02-01 Covariances were taken from JENDL-3.2 covariance file except
for MF/MT=31/455, 31/456/, 33/18, and 33/102, which were
evaluated by Matsunobu./8/
MF=2 Resonance Parameters
MT=151
2200-m/s cross sections and calculated res. integrals
2200 m/s Res. Integ.
total 588.38 b -
elastic 11.97 b -
fission 531.16 b 773 b
capture 45.25 b 138 b
MF=3 Neutron Cross Sections
Smooth part (above 30 keV)
MT=18 Fission
Results of recent simultaneous evaluation of fission cross
sections /2/ were adopted.
MF=5 Energy Distributions of Secondary Neutrons
MT=16,17,91
Calculated with pre-compound and multi-step evaporation
theory code EGNASH /3,4/.
MT=455 Delayed neutron spectrum.
Summation calculation made by Brady and England /5/ was
adopted.
MF=31 Covariances of Average Number of Neutrons per Fission
MT=452
Constructed from MT=455 and 456.
MT=455
Based on experimental data. A chi-value was 0.13.
MT=456
Based on experimental data. A chi-value was 0.96.
MF=32 Covariances of Resonance Paremeters (ref.6)
MT=151
Resolved resonance
Based on the SAMMY analysis by Derrien /1/.
Unresolved resonance
The covariances were obtained by using kalman.
MF=33 Covariances of Cross Sections (ref.6)
MT=1
Based on experimental data. A chi-value was 0.244.
MT=2
Constructed from mt=1, 4, 16, 17, 18, and 102.
MT=4
Based on experimental data. A chi-value was 0.151.
MT=16
Based on experimental data.
MT=17
Taken from mt=16
MT=18
The covariances were obtained by the simultaneous evaluation.
/2/
MT=102
Based on experimental data on alpha values. A chi-value was
0.186.
MF=34 Covariances of Angular Distributions (ref.6)
MT=2
The covariances of p1 coefficients were obtained by using
kalman. A chi-value was 1.474.
MF=35 Covariances of Energy Distributions
MT=18
The covariances were obtained by using kalman./7/
References
1) Derrien H.: J. Nucl. Sci. Technol., 31, 379 (1994)
2) Kawano T. et al.: JAERI-Research 2000-004 (2000).
3) Yamamuro N.: JAERI-M 90-006 (1990).
4) Young P.G. and Arthur E.D.: LA-6947 (1977).
5) Brady M.C. and England T.R.: Nucl. Sci. Eng., 103, 129(1989).
6) Shibata K. and Hasegawa A.: JNC TJ9400 2000-004 (2000)
[in Japanese].
7) Kawano T. et al.: JAERI-Research 99-009 (1999) [in Japanese].
8) Matsunobu H.: Private communication (2001).
******************** JEDL-3.2 ************************************
92-U -233 SAEI+ Eval-Mar87 H.Matsunobu,Y.Kikuchi,T.Nakagawa
Dist-Sep89 Rev2-Apr94
History
82-06 Evaluation for JENDL-2 was made by N. Asano (SAEI),
H. Matsunobu (SAEI) and Y.Kikuchi(JAERI).
87-03 Re-evaluation for JENDL-3 was made by H.Matsunobu (SAEI)
Main part of revision was the cross sections above 10 keV
and angular and energy distributions of neutrons.
Data were compiled by T. Nakagawa (JAERI).
94-04 JENDL-3.2.
Resonance parameters reevaluated by H.Derrien (JAERI)/1/
Cross sections reevaluated by H.Matsunobu(SAEI)
Fission spectrum reevaluated by T.Ohsawa(Kinki univ.)
Compiled by T.Nakagawa (NDC/JAERI)
***** Modified parts for JENDL-3.2 ********************
(2,151); New analysis with SAMMY
MF=3 ; all data except fission cross section below 6.75
MeV and total cross section
MF=4 ; for inelastic scattering
(5,18)
***********************************************************
MF=1 General Information
MT=451 Comments and dictionary
MT=452 Nu-total
Sum of Nu-d and Nu-p
MT=455 Nu-d
Below 4 MeV
Nu-d = 0.0075094 + 4.627E-5*ln(E(MeV))
Between 4 and 20 MeV
Based on the data of Masters et al. /2/ and Evans et al.
/3/.
MT=456 Nu-p
Renormalization was made to 3.756 of Cf-252.
Below 1 MeV
Nu-p = 2.486 + 0.1121*(E-DE),
where DE is difference of average fragment kinetic energy
between incident and thermal neutron energies. It was
taken from data of Boldeman et al. /4/.
Between 1 and 2.73 MeV
Nu-p = 2.436 + 0.1279*E
Between 2.73 and 7.47 MeV
Nu-p = 2.327 + 0.1678*E
Above 7.47 MeV
Nu-p = 2.857 + 0.09689*E
MF=2 Resonance Parameters
MT=151
a) Resolved resonance region ( 1 eV to 150 eV)
Resolved resonance parameters for the Reich-Moore formula
were obtained by using SAMMY/5/. Details are given in
Appendix.
b) Unresolved resonance region ( 0.15 keV to 30 keV)
Parameters were deduced with ASREP code /6/ so as to
reproduce the evaluated cross sections in this energy
region.
2200-m/s cross sections and calculated res. integrals
2200 m/s Res. Integ.
total 588.38 b -
elastic 11.97 b -
fission 531.16 b 774 b
capture 45.25 b 138 b
MF=3 Neutron Cross Sections
Smooth part (above 30 keV)
MT=1 Total
Based on the data of Poenitz /7,8/. Between 10 and 48
keV, cross-section curve calculated with the statistical-
model code CASTHY /9/ and the coupled-channel theory code
ECIS /10/ was normalized at 48 keV.
MT=2 Elastic
Obtained by subtracting non-elastic scattering cross section
from the total cross section.
MT=4 and 51-64,91 Inelastic scattering
Calculated with CASTHY /9/ and ECIS /10/. Coupled levels were
first three levels. Deformed OMP recommended by Haouat et
al. /11/, was slightly modified so as to reproduce the
experimental data of Smith et al. /12/, and spherical OMP was
the same as that used for JENDL-2. In the energy range above
8.25 MeV, the cross section was approximated by using an
extponential-type fuction, because the cross section curve
obtained by CASTHY and ECIS showed large fluctuation.
Deformed OMP
V =46.4-0.3*E , Ws=3.5 +0.4*E , Vso=6.2 (MeV)
r0=1.26 , rs=1.26 , rso=1.12 (fm)
a0=0.63 , b =0.52 , aso=0.47 (fm)
Beta-2=0.20, Beta-4=0.074
Spherical OMP
V =41.8-0.20*E+0.008*E**2, Ws=6.50-0.15*E, Vso=6.0 (MeV)
r0=1.31 , rs=1.36 , rso=1.32 (fm)
a0=0.57 , b =0.44 , aso=0.50 (fm)
(dir. W.S.)
Level scheme was taken from Ref. /13/.
No. Energy(MeV) Spin-Parity
g.s. 0.0 5/2 + *
1 0.04035 7/2 + *
2 0.0922 9/2 + *
3 0.1551 11/2 + *
4 0.29882 5/2 -
5 0.31191 3/2 +
6 0.3208 7/2 -
7 0.34047 5/2 +
8 0.3537 9/2 -
9 0.397 11/2 -
10 0.39849 1/2 +
11 0.41576 3/2 +
12 0.5039 7/2 -
13 0.5467 5/2 +
14 0.5971 7/2 +
Above 0.6 MeV, assumed to be overlapped. Levels with asterisk
were coupled in the ECIS calculation.
MT=16,17 (n,2n) and (n,3n)
Calculated by using the EGNASH-2 code /14/. The (n,2n) cross
section was normalized to fission-spectrum-averaged value of
0.00408 b measured by Kobayashi et al./15/. The same
normalization factor was also applied to the (n,3n) cross
section.
MT=18 Fission
Based on the experimental data of Gwin et al. /16/, Carlson
et al. /17/, Manabe et al. /18/, Kanda et al. /19/, Iwasaki
et al. /20/, Meadows /21/, Lisowski et al./22/ and the
fission cross section of U-235 obtained by the simultaneous
evaluation /23/ and measured by Carlson et al./24/ between
13.25 and 20 MeV.
MT=102 Capture
In the energy range from 30 keV to 1 MeV, the alpha values
measured by Hopkins and Diven /25/ were multiplied by the
fission cross section. In the high energy region, values
calculated with CASTHY and ECIS were normalized to 0.0578 b
at 1 MeV.
MT=251 Mu-bar
Calculated with CASTHY and ECIS.
MF=4 Angular Distributions of Secondary Neutrons
MT=2, 51-64 and 91
Calculated with CASTHY and ECIS.
MT=16,17 and 18
Assumed to be isotropic in the Lab system.
MF=5 Energy Distributions of Secondary Neutrons
MT=16,17,91
Calculated with PEGASUS /26/.
MT=18 Fission spectrum
Distributions were calculated with the modified Madland-Nix
model/27,28/. The compound nucleus formation cross sections
for fission fragments (FF) were calculated using Becchetti-
Greenlees potential/29/. Up to 4th-chance-fission were
considered at high incident neuttron energies. The Ignatyuk
formula/30/ were used to generate the level density
parameters.
Parameters adopted:
Total average FF kinetic energy = 172.311-0.0212*E(MeV)
Average energy release = 188.438 MeV
Average mass number of light FF = 95
Average mass number of heavy FF = 139
Level density of the light FF = 9.999- 10.094
Level density of the heavy FF = 11.89 - 12.20
Note that the parameters vary with the incident energy
within the indicated range.
MT=455 Delayed neutrons
Recommendation by Saphier et al. /31/ was adopted.
References
1) Derrien H.: to be published in J. Nucl. Sci. Technol. (1994)
2) Master C.F. et al.: Nucl. Sci. Eng., 36, 202 (1969).
3) Evans A.E. et al.: Nucl. Sci. Eng., 50, 80 (1973).
4) Boldeman J.W. et al.: Nucl. Phys., A265, 337 (1976).
5) Larson N.: ORNL/TM-9179/R1 (1985).
6) Kikuchi Y.: to be published.
7) Poenitz W.P. et al.: Nucl. Sci. Eng., 78, 333 (1981).
8) Poenitz W.P. et al.: ANL/NDM-80 (1983).
9) Igarasi S. and Fukahori T.: JAERI 1321 (1991).
10) Raynal J.: ECIS.
11) Haouat G., et al.: Nucl. Sci. Eng., 81, 491 (1982).
12) Smith A.B. et al.: 1982 Antwerp, p.039 (1982).
13) Lederer D.G. and Shirley V.S.: Table of Isotopes, 7th Ed.
(1978).
14) Yamamuro N.: JAERI-M 90-006 (1990).
15) Kobayashi K.: J. Nucl. Sci. Technol., 10, 668 (1973).
16) Gwin R. et al.: Nucl. Sci. Eng., 59, 79 (1976).
17) Carlson G.W. and Behrens J.W.: Nucl. Sci. Eng., 66, 205 (1978)
18) Manabe F., et al. : 1987 Annual Meeting of Atomic Energy
Society of Japan, Nagoya, p.167 (1987) in Japanese.
19) Kanda K., et al.: 1985 Santa-Fe, p.569 (1985).
20) Iwasaki T., et al.: private communication (1987).
21) Meadows J.W.: Nucl. Sci. Eng., 54, 317 (1974).
22) Lisowski P.W.: 1991 Juelich, p.732 (1992).
23) Kanda Y. et al.: 1985 Santa Fe, 2, 1567 (1986).
24) Carlson A.D. et al.: 1991 Juelich, p.518 (1992).
25) Hopkins J.C. and Diven B.C.: Nucl. Sci. Eng., 12, 169 (1962).
26) Iijima S, et al.: JAERI-M 87-025, p.337 (1987).
27) Madland D.G. and Nix J.R.: Nucl. Sci. Eng., 81, 213 (1982).
28) Ohsawa T. and Shibata T.: 1991 Juelich Conf., 965 (1992).
29) Becchetti Jr.F.D. and Greenlees G.W.: Phys. Rev., 182, 1190
(1969).
30) Ignatyuk A.V.: Sov. J. Nucl. Phys., 29, 450 (1979).
31) Saphier D., et al.: Nucl. Sci. Eng., 62, 660 (1977).
*****************************************************************
Appendix RESONANCE DATA ,JAERI DECEMBRE 1992
*****************************************************************
The Reich-Moore R-matrix resonance parameters were obtained
from sequencial Bayesian fits of selected experimental total, fis-
sion and capture cross sections performed with the computing code
SAMMY. The selected experimental data were the following:
1) total cross sections measured by Pattenden/1/, Moore/2/,
Kolar/3/, Harvey/4/;
2) fission cross sections measured by Weston/5,6/, Blons/7/,
Deruyter/8/, Wagemans/9/.
3) capture cross sections measured by Weston/5,6/.
In the low energy range the data of Pattenden,Moore,Harvey,
Kolar, Weston, Deruyter and Wagemans were considered.In the energy
range from 15 eV to 150 eV, only the data from Kolar, Blons and
Weston could be analysed owing to the poor resolution of the other
data. Some of the data were renormalized to the Axton standard
/10/ at 0.0253 eV. The fission cross section measurement of Weston
/5/ available in the energy range above 1 eV was renormalised to
the data of Wagemans/9/ over the energy range from 1 eV to 20 eV,
resulting in an increase of the cross section by 2.4% compared to
the original EXFOR file. The fission cross section measurement of
Blons available in the energy range above 15 eV was renormalized
to the the data of Weston over the energy range from 15 eV to 150
eV, resulting in an increase of the cross section by 2.9% compared
to the data in the original EXFOR file. The total cross section of
Kolar needed a background correction of (2.3-0.038E) barn, E in
eV, in the energy range from 77 eV to 150 eV, corresponding to 0
to 1.5% of the measured transmission. These renormalizations and
background corrections were performed after preliminary fits of
the data available from the EXFOR file in order to realize a
consistency of +-2% among the cross section of the experimental
data base. The final SAMMY fits were performed without renormali-
zation and background correction parameters
The transmission data of Pattenden, Moore, Harvey and Kolar
are not available from the EXFOR file and were not requested from
the authors. The SAMMY fits were performed on the experimental ef-
fective total cross sections using the sample thicknesses and the
experimental resolution to calculate the theoritical effective
cross sections. Enough informations were found in the publications
by the authors to ensure the accuracy of the calculations.
Due to the high resolution of the transmission measurements of
Kolar(100 m flight path) and of the fission measurements of Blons
(50 m flight path and sample cooled down at liquid nitrogen tempe-
rature) the analysis could be performed up to 150 ev neutron ener-
gy. The high resolution fission cross section of Cao/11/ were not
included in the experimental data base owing to a severe problem
of the renormalization of the data.
The capture cross sections of Weston were included in the fits
below 30 eV only. Above 30 eV the statistical accuracy of the data
was too poor and the try and error method was used in a prelimina-
ry work to obtain the capture width of some strong capture reson-
ances. The capture width of the other resonances was kept at a
constant value of 41 meV close to the average value obtained by
fitting the energy range below 30 eV. Some resonances not pertain-
ing to 233U were disclosed in the experimental data and were iden-
tified as 195Pt resonances. The experimental data of Table 2 were
roughly corrected for these resonances.
The values of the cross sections obtained by Axton at 0.0253
eV were included in all the experimental data available in the
thermal range with the small error bars obtained by Axton, in
order to ensure the best agreement between the calculated and the
evaluated thermal values. The values calculated from the resonance
parameters are the followings:
Calculation Axton
(RESENDD 0.1% 300 K) Evaluation
Fission 531.29 b 530.70+-1.34 b
Capture 45.27 b 45.62+-0.70 b
Scattering 11.99 b 12.19+-0.67 b
Tables 1 and 2 show the average cross sections calculated
from the resonance parameters compared with the average experimen-
tal data and with average JENDL-3, ENDF/B-VI and JEF-2 data.
Table 1 Fission Cross Sections
-------------------------------------------------------------
Energy Wagem Deruy Westo Blons Calcu JENDL ENDF6 JEF2
Range(eV)
-------------------------------------------------------------
0.021-0.031 525.6 526.7 526.8 526.5 528.8 523.9 520.6
0.031-0.082 362.9 363.5 363.9 361.7 363.9 361.9 359.7
0.082-1.000 151.3 150.9 150.6 150.1 149.4 149.0 148.6
1.000-2.100 388.8 387.7 391.7 387.9 383.0 378.9 382.1
2.100-2.750 204.4 204.6 207.5 204.6 205.9 198.1 198.8
2.750-3.000 50.1 53.4 51.9 50.2 52.9 50.6 50.8
3.000-15.00 106.2 105.6 104.9 104.3 103.6 101.2 101.5
0.021-15.00 134.2 133.5 133.5 132.5 131.7 129.1 129.5
15.00-30.00 95.03 94.60 95.51 96.49 91.80 92.69
30.00-50.00 40.13 40.30 40.27 40.19 38.85 39.16
50.00-75.00 40.66 40.49 40.53 40.79 35.80 39.90
75.00-100.0 35.57 36.70 36.03 36.58 33.36 32.74
100.0-125.0 36.84 36.89 36.97 31.78 29.94 28.94
125.0-150.0 21.29 20.29 20.78 16.30 22.10 26.25
15.00-150.0 41.39 41.48 41.45 39.91 38.49 40.05
--------------------------------------------------------------
Table 2 Capture Cross Sections
-------------------------------------------------------------
Energy Weston Calcul JENDL3 ENDF6 JEF2.2
Range(eV)
-------------------------------------------------------------
0.021-0.031 45.17 44.90 44.82 45.40 45.54
0.031-0.082 32.51 32.57 32.45 32.58 32.68
0.082-1.000 14.06 14.44 13.99 13.24 13.13
1.000-2.100 66.83 66.54 70.54 67.46 67.31
2.100-2.750 111.83 110.67 106.25 112.04 110.80
2.750-3.000 7.50 8.25 8.85 7.53 5.74
3.000-15.00 17.43 17.61 19.51 17.66 17.02
0.021-15.00 24.85 24.97 26.57 24.22 24.43
15.00-30.00 13.25 13.97 11.92 13.27 12.67
30.00-50.00 5.21 5.81 4.85 5.47 5.00
50.00-75.00 4.91 5.38 4.42 3.80 5.25
75.00-100.0 8.71 9.07 5.39 4.30 5.33
100.0-125.0 5.37 6.01 3.55 3.88 4.63
125.0-150.0 3.38 3.78 2.12 3.54 4.12
15.00-150.0 6.39 6.90 4.91 5.16 5.73
--------------------------------------------------------------
The experimental capture data of Weston was increased by
a background correction according to the evaluation of Reynolds
et al./12/ and renormalized to the original value of Weston in
the energy range 1.0 eV to 2.75 eV.
RESONANCE INTEGRAL FISSION
Energy range this work JENDL-3 ENDF/B-6 JEF-2
------------------------------------------------------
0.5 eV-150 eV 710.34 710.53 691.08 697.18
150 eV-20 MeV 64.25 63.34 65.29
0.5 eV-20 MeV 774.79 754.43 762.47
------------------------------------------------------
RESONANCE INTEGRAL CAPTURE
Energy range this work JENDL-3 ENDF/B-6 JEF-2
------------------------------------------------------
0.5 eV-150 eV 131.92 131.77 128.79 127.51
150 eV-20 MeV 6.65 7.58 7.24
0.5 eV-20 MeV 138.42 136.37 134.75
------------------------------------------------------
References of Appendix
1) PATTENDEN et al.: Nucl. Sci. Eng., 17, 404 (1963)
2) MOORE et al.: Phys. Rev., 118, 714 (1960)
3) KOLAR et al.: 1970 Helsinki, Vol.I, 387 (1970)
4) HARVEY et al.: 1979 Knoxville, p.690 (1979)
5) WESTON et al.: Nucl. Sci. Eng., 34, 1 (1968)
6) WESTON et al.: Nucl. Sci. Eng., 42, 143 (1970)
7) BLONS et al.: Nucl. Sci. Eng., 51, 130 (1973)
8) DERUYTER et al.: Nucl. Sci. Eng., 54, 423 (1974)
9) WAGEMANS et al.: 1988 Mito, 91 (1988)
10) AXTON et al.: BCMN Report, GE/PH/01/86 (1986)
11) CAO et al.: 1970 Helsinki. Vol.I, 419 (1970)
12) REYNOLDS et al.: KAPL-M-7323 (1973)
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