8-O - 16
8-O - 16 JNDC EVAL-DEC83 Y.KANDA(KYU) T.MURATA(NAIG)+
JAERI-M 90-012 DIST-MAY10 20090629
----JENDL-4.0 MATERIAL 825
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
83-12 New evaluation for JENDL-3
Sub-working group on evaluation of O-16,
Working group on nuclear data for fusion,
Japanese Nuclear Data Committee
In charge
sig-t Y.Nakajima K.Shibata(jaeri)
sig-el T.Murata(naig)
sig-in S.Tanaka(jaeri)
capture T.Asami(jaeri)
(n,2n),(n,p),(n,d),(n,alpha) Y.Kanda(kyu)
Compilation
Evaluated data were compiled by K.Shibata.
84-07 Data of mf=4 (mt=16,91) were revised.
Comment was also modified.
87-01 Data of mf=3 (mt=51-64,67), mf=4 (mt=51-55) and mf=5(mt=16)
were modified (S.Chiba, jaeri). Comment was also modified.
90-10 mf=5 (except mt=91), mf=12, mt=102 modified.
93-12 Capture and gamma production cross sections were modified.
08-07 Total and elastics scattering cross sections were modified
below 3 MeV. The elastic angular distributions were
replaced with new R-matrix calculations between 100 keV and
3 MeV.
09-04 The (n,a) cross sections was modified.
09-06 The interpolation of MF/MT=12/102 was changed to 2.
***** modified parts for JENDL-3.2 ******************************
(3,102) Reevaluated by K. Shibata.
(3,2),(3,3) Recalculated
(12,102) Modified due to energy conservation
(12,51;57;62) 510 keV gammas incorporated
(13,3) Reevaluated by T. Asami (de)
******************************************************************
***** modified parts for JENDL Fusion File 96/1/26 *************
(3,102) Calculated by A. Mengoni (enea)
(3,2),(3,3) Recalculated
******************************************************************
2002-1 Compiled by K.Shibata (jaeri) for JENDL-3.3.
***** modified parts for JENDL-3.3 2001/5/23 *******************
(1,451) Modified.
(3,1),(3,2) Recalculated
(3,16) Corrected
The JENDL-3.2 data were ten times larger than the
measurement /2/ by mistake.
(3,3) Deleted
(3,251) Deleted
(4,2) Transformation matrices were deleted.
(5,22),(5,28) Distributions at threshold were modified.
Interpolation was changed to 22.
(12,51-107) Calculated.
(13,3) Deleted.
(14,51-107) Prepared.
(15,3) Deleted.
(15,51-107) Calculated.
(33,1-107) Taken from JENDL-3.2 covariance file except for
mt=16. The covariance for mt=16 was revised on
the basis of experimental data.
(34,2) Taken from JENDL-3.2 covariance file.
******************************************************************
2009-04 Compiled by K.Shibata (jaea) for JENDL-4
***** modifications for JENDL-4 2008/07/02 *********************
(1,451) Modified
(3,2) R-matrix calculations below 3 MeV
(3,1) Re-calculated from partial cross sections
(4,2) R-matrix calculations between 100 keV and 3 MeV
(3,107) The data were replaced with those of ENDF/B-VII.0
below 6.5 MeV.
******************************************************************
mf=1 General information
mt=451 Descriptive data
mf=2 Resonance parameters
mt=151 Scattering radius only.
mf=3 Cross sections
Thermal cross sections and resonance integrals at 300 K
----------------------------------------------------------
0.0253 eV res. integ. (*)
(barns) (barns)
----------------------------------------------------------
Total 3.9624E+00
Elastic 3.9646E+00
n,gamma 1.8988E-04 6.7337E-04
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
mt=1 Sig-t
Below 3 MeV, the total cross section was calculated
with the R-matrix theory.
Above 3 MeV, based on the experimental data of
Cierjacks et al./1/.
*********************************************************
For JENDL-4, data were modified below 3 MeV. See above.
*********************************************************
mt=2 Sig-el
Below 3 MeV, calculated with the R-matrix theory.
Above 3 MeV, the elastic scattering cross section was
obtained by subtracting the reaction cross sections from
the total cross section.
*********************************************************
For JENDL-4, data were modified below 3 MeV. See above.
*********************************************************
mt=4 Total inelastic
Sum of mt=51 to 91.
mt=16 (n,2n)
Based on experimental data/2/.
mt=51-79,91 Sig-in
Shape of the excitation functions was calculated with
the statistical model.
The optical potential parameters are the following:
V = 48.25-0.053E, Ws = 3.0 + 0.25E, Vso = 5.5 (MeV)
r = 1.255 , rs = 1.352 , rso = 1.15 (fm)
a = 0.536 , b = 0.205 , aso = 0.50 (fm).
Level scheme
no Energy(MeV) Spin-parity
g.s. 0.0 0+
1 6.0490 0+
2 6.1300 3-
3 6.9170 2+
4 7.1169 1-
5 8.8720 2-
6 9.6300 1-
7 9.8470 2+
8 10.360 4+
9 10.960 0-
10 11.080 3+
11 11.100 4+
12 11.520 2+
13 11.600 3-
14 12.050 0+
15 12.440 1-
16 12.530 2-
17 12.800 0-
18 12.970 2-
19 13.020 2+
20 13.090 1-
21 13.120 3-
22 13.260 3-
23 13.660 1+
24 13.870 4+
25 13.980 2-
26 14.030 0+
27 14.100 3-
28 14.300 4+
29 14.400 5+
Continuum levels were assumed above 14.4 MeV.
Constant temperature of 3.4 MeV was used.
For the inelastic scattering to the second and third
levels, the (n,n')gamma data of Nordborg et al./3/ and
Lundberg et al./4/ below 10 MeV.
For mt=51 to 55, the 14 MeV cross sections were
normalized to the experimental data/5/-/8/.
Cross sections for mt=56-64 and 67 were normalized to
reproduce the ddx data at 14 MeV/8/,/9/.
mt=102 Capture
1/v curve normalized to the recommended value in the
4th edition of BNL-325 /10/ at 0.0253 eV.
Between 1 eV and 1 MeV, model calculations (direct
capture and resonance) were performed by A. Mengoni
(enea)/28/.
Above 1 MeV, a value of 0.1 mb was assumed by
considering inverse reaction data.
mt=103 (n,p)
Based on experimental data/11/-/14/.
mt=104 (n,d)
Based on the evaluation of Foster, Jr. and Young /15/.
mt=107 (n,alpha)
Based on experimental data/3/,/16/-/21/.
For JENDL-4, the measured (n,a) cross sections, which
were coverted from the inverse-reaction data/18,21,32/,
were compared with the existing libraries. As a result,
it was found that the ENDF/B-VII.0 data reproduce the
experimental data fairly well below 6.5 MeV. Therefore,
we decided to replace the (n,a) data with those of
ENDF/B-VII.0 below 6.5 MeV. Above 6.5 MeV, the cross
sections remain unchanged from JENDL-3.3.
mf=4 Angular distributions of secondary neutrons
mt=2
10e-5 eV to 3 MeV R-matrix calculation
3 MeV to 5 MeV Based on the experimental data of
Lister and Sayres /22/.
5 MeV to 9 MeV Multi-level formula/23/.
9 MeV to 15 MeV Based on the experimental data of
Glendinning et al./24/
15 MeV to 20 MeV Calculated with the spherical
optical model. The potential
parameters are the same as those
given in Sig-in.
*********************************************************
For JENDL-4, data were modified between 100 keV and 3
MeV. See above.
*********************************************************
mt=16
Assumed to be isotropic in the laboratory system.
mt=51-79
Calculated with the statistical model.
For mt=51, 52 and 55, experimental data/8/ at 14.2 MeV.
For mt=53 and 54 ENDF/B-IV was adopted.
mt=91
Isotropic distributions in the center of mass system
were transformed into the ones in the laboratory system.
The formula is given in ref./25/.
mf=5 Energy distribution for secondary neutrons
mt=16
Evaporation spectrum was assumed. Constant temperature
was deduced from the experimental data of Chiba et al.
/26/ for Li-7 according to the Sqrt(E/a) law.
mt=22,28
Calcualted by GNASH /27/.
mt=91
Evaporation spectrum was assumed. Constant temperature
of 3.4 MeV was determined from the stair case plotting.
mf=12 Photon production multiplicities
mt=22,51-55,59,61,63,66-68,103,107
Calculated with GNASH/27/.
mt=102
Calculated with CASTHY/29/.
Below 280 keV, based on the data measured by Igashira
et al./30/
mf=14 Photon angular distributions
mt=22,51-55,59,61,63,66-68,102,103,107
Isotropic
mf=15 Photon energy distributions
mt=22,103,107
Calculated with GNASH/27/.
mt=102
Calculated with CASTHY/29/.
mf=33 Covariances of cross sections (ref. 31)
mt=1
Based on experimental data. A chi-value was 6.53.
mt=2
Constructed from mt=1, 16, 22, 28, 51-91, 102, 103, 104,
and 107.
mt=4
Constructed from mt=51-91.
mt=16
Based on experimental data.
mt=22
Based on systematics.
mt=28
Based on systematics.
mt=51-91
The covariances were estimated by using kalman system.
A chi-value was 2.45.
For mt=52,53, based on experimental data between 7 and
11 MeV.
mt=102
Based on experimental data.
mt=103
Based on experimental data.
mt=104
Based on experimental data.
mt=107
Based on experimental data.
mf=34 Covariances of angular distributions
mt=2
Based on experimental data and model calculations.
References
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2) Brill,O.D. et al.: Soviet Phys. Doklady, 6, 24 (1961).
3) Nordborg,C. et al.: Nucl. Sci. Eng., 66, 75 (1978).
4) Lundberg,B. et al.: Phys. Scr. 2, 273 (1970).
5) Bauer,R.W. et al.: Nucl. Phys., 47, 241 (1963).
6) McDonald,W.J. et al.: Nucl. Phys., 75, 353 (1966).
7) Meier,D. et al.: EXFOR 20907,007 (1969).
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Santa Fe, 1985, p223.
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10)Mughabghab,S.F. et al.: Neutron Cross Sections Vol.1,
Academic Press, 1981.
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1 (1967) 225.
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Technology, Mito, 1988, p.557, (1988).
24)Glendinning, S.G. et al.: Nucl. Sci. Eng., 82, 393 (1982).
25)Nakagawa,T: JAERI-M 84-103 (1984).
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27)Young,P.G. and Arthur,E.D.: LA-6947 (1977).
28)Mengoni A.: Private communication (1995).
29)Igarasi S. and Fukahori T.: JAERI 1321 (1991).
30)Igashira M. et al.: private communication (1993).
31)Shibata,K. et al.: JAERI-Research 97-074 (1997).
32)Harissopulos,S. et al.: Phys. Rev., C72, 062801 (2005).