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74-W -182 KHI,NEDAC EVAL-MAR87 T.WATANABE(KHI), T.ASAMI(NEDAC)
DIST-JAN09 20090105
----JEFF-311 MATERIAL 7431
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
** **
** Original data taken from: JEFF-3.1 **
** **
******************************************************************
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JENDL-3.3 **
** **
******************************************************************
HISTORY
87-03 New evaluation was made for JENDL-3.
87-03 Compiled by T.Asami.
94-01 JENDL-3.2.
Compiled by T.Nakagawa (ndc/jaeri)
00-03 Reevaluation was made by T.Asami.
01-11 Compiled by K.Shibata (ndc/jaeri)
***** modified parts for JENDL-3.3 from JENDL-3.2 *****
(3,2) re-calculated
(3,203,207) added
(3,251) deleted
(4,2) transformation matrix deleted
(4,16,17,22,28,91) deleted
(5,16,17,22,28,91) deleted
(6,16,17,22,28,91) taken from JENDL fusion file
(6,203,204,207) taken from JENDL fusion file
(12,22-107) evaluated newly
(13,3) evaluated newly
(14,3-107) isotropic distributioins
(15,3-107) evaluated newly
***********************************************************
The JENDL fusion file /1/ and the modification of JENDL-3.2
from JENDL-3.1 as follows:
-------------------------------------------------------------
JENDL fusion file /1/ (as of Jan. 1994)
Evaluated by K.Kosako (nedac) and S. Chiba (ndc/jaeri)
Compiled by K.Kosako.
Data were taken from JENDL-3.1 except for the following:
- The inelastic scattering cross sections to the levels
above mt=59 and angular distributions of inelastically
scattered neutrons (except continuum inelastic) were
calculated with casthy2y and dwucky in sincros-ii
system/2/ including contributions from direct reactions.
- The (n,2n), (n,3n), (n,na), (n,np), (n,p), (n,d) and
(n,a) reaction cross sections (mt=16, 17, 22, 28, 103,
104, 107) were calculated by egnash2 in the sincros-ii.
- Energy distributions of secondary neutrons were replaced
by those calculated by egnash2. The ddx's of the
continuum neutrons were calculated by Kumabe's systema-
tics /3/ using f15tob /1/. The precompound/compound
ratio was calculated by the sincros- ii code system.
- Optical-model, level density and other parameters used in
the sincros-ii calculation are described in ref./2/.
level schemes were determined on the basis of ENSDF/4/.
For JENDL-3.2 and JENDL fusion file, all cross section data
except for the total, elastic scattering, capture and
some of the inelstic scattering cross sections were
calculated with sincros-ii system/2/ by adopting
Walter-Guss omp modified by Yamamuro/2/ for neutron,
Perey omp /12/ for proton, Lemos omp modified by Arthur and
Young/13/ for alpha, Lohr-Haeberli omp/14/ for deuteron,
Becchettii-Greenlees omp/15/ for triton and he-3, and standard
level density parameters of sincros-ii system.
-------------------------------------------------------------
mf=1 General information
mt=451 Descriptive data and dictionary
mf=2 Resonance parameters
mt=151 Resolved resonance parameters
Resolved parameters for mlbw formula were given in the energy
region from 1.0e-5 eV to 12 keV.
Parameters were evaluated in examining both the experimental
data/5,6,7/ and the recommended data in ref./8/. For unknown
radiative width, an average value of 53 milli-eV was assumed.
Parameters for a negative resonance were selected so that the
2200 m/s cross sections agreed with a recommended capture cross
section of 20.7 barns/8/ and the experimental data for total
cross sections around thermal energies. The scattering radius
was assumed to be 7.5 fermi.
calculated 2200 m/sec cross sections and resonance integrals
are as follows:
2200 m/s cross section(b) res. integral(b)
elastic 8.84
capture 20.7 628.
total 29.6
mf=3 Neutron cross sections
Below 12 keV, zero background cross section was given and all
the cross-section data are reproduced from the evaluated
resolved resonance parameters.
For JENDL-3.1, above 12 keV, the total and partial cross
sections were given mainly based on the theoretical calcula-
tions. The total, elastic and inelastic scattering, and capture
cross sections were calculated with the coupled-channel model
and the spherical optical-statistical model. Tthe calculations
were performed with a combined program of casthy/9/ and
ecis/10/. The optical potential parameters used are:
V = 48.83 - 0.0809*En, Vso = 5.6 (MeV)
Ws = 6.73 - 0.0536*En, Wv = 0 (MeV)
r = 1.168, rs = 1.268, rso = 1.592 (fm)
a = 0.617, aso = 0.664, b = 0.563 (fm)
The deformed potential parameters were taken from the work of
Delaroche/11/.
mt=1 Total
Below 12 keV, reproduced from the evaluated resolved resona-
nce parameters.
Above 12 keV, calculated with the combined program of the ecis
and casthy codes. almost the same as JENDL-3.1.
mt=2 Elastic scattering
Obtained by subtracting the sum of the partial cross sections
from the total cross section.
mt=4, 51-70, 91 Inelastic scattering
The data of mt=51 to 58 were calculated with the combined
program of ecis/10/ and casthy /9/. These cross sections
are the same as JENDL-3.1 except that new calculation
was made at several energy points. The other cross sections
were calculated with sincros-ii for JENDL fusion file. The
level scheme was based on ref./4/ contributions of the direct
process was calculated for the levels marked with '*'.
no. mt energy(MeV) spin-parity (direct process)
g.s. 0.0 0+
1 51 0.1001 2+ *
2 52 0.3294 4+ *
3 53 0.6805 6+ *
4 54 1.1358 0+
5 55 1.1444 8+ *
6 56 1.2214 2+
7 56 1.2574 2+
8 56 1.2892 2-
9 57 1.3311 3+
10 57 1.3738 3-
11 58 1.4428 4+
12 58 1.4875 4-
13 58 1.5102 4+
14 58 1.5532 4-
15 58 1.6213 5-
16 58 1.6235 5+
17 58 1.6604 5-
18 59 1.7119 10+ *
19 60 1.7568 6+
20 61 1.7654 4+
21 62 1.7690 5-
22 63 1.8097 5-
23 64 1.8109 6-
24 65 1.8134 4-
25 66 1.8295 6-
26 67 1.8331 2-
27 68 1.8560 2+
28 69 1.8569 2+
29 70 1.8712 1-
Levels above 1.872 MeV were assumed to be overlapping. Data of
levels 6-8, 9-10 and 11-17 were lumped as is indicated in the
above table. The direct inelastic scattering cross section was
calculated also for the levels at 1.959, 2.372, 2.493, 3.112,
3.397, 3.6, 4.0, 4.5, 5.0, 5.5 and 6.0 MeV and added to mt=91.
Finally, the data for mt=51,52,53,54,55,56 and 91 were adjusted
to reproduce the benchmark integral data/16/.
mt=16, 17, 22, 28, 103, 104, 107
(n,2n), (n,3n), (n,na), (n,np), (n,p), (n,d), (n,a)
Theoretical calculation was made with sincros-ii. The results
were normalized to
(n,2n) 2.161 b at 14.7 MeV measured by Qaim/17/,
(n,p) 0.0059 b at 14.7 MeV measured by Qaim/17/,
(n,d)+(n,np) 0.002 b at 14.7 MeV (systematics of Qaim/17/),
(n,a) 0.002 b at 14.7 MeV (systematics of Qaim/17/).
mt=102 Capture
Below 12 keV, reproduced from the evaluated resolved resona-
nce parameters.
Above 12 keV, calculated with the casthy code/9/ and normalized
to 72+-9 mb at 500 keV of voignier et al./18/.
Above 3 MeV, a straight line in log-log scale was adopted
assuming 1.0 milli-barn at 14 MeV.
mt=203 Total proton production
Sum of mt=28 and 103.
mt=204 Total deuteron production
Equal to mt=104.
mt=207 Total alpha production
Sum of mt=22 and 107.
mf=4 Angular distributions of secondary neutrons
mt=2
Calculated with the casthy code/9/.
mt=51-58
Calculated with the combined program of the casthy/9/ and
ecis/10/ codes.
mt=59-70
Based on casthy2y calculation.
mf=6 Energy-angle distributions of secondary particles
mt=16, 17, 22, 28, 91
Based on Kumabe's systematics/1,3/.
mt=203,204,207
Based on Kalbach's systematics/1,19/.
mf=12 Photon production multiplicities and transition probability
arrays
mt=22,51-70,102,103,107
Below 1.88238 MeV, given as multiplicities
calculated with the egnash code/2/ and processed by the
gamfil2 code/20/.
mt=102 was calculated with the casthy code/10/.
mf=13 Photon production cross sections
mt=3
Calculated with the egnash code/2/ and processed by the
gamfil2 code/20/.
mf=14 Photon angular distributions
mt=3,22,51-70,102,103,107
Assumed to be isotropic distributions
mf=15 Continuous photon energy spectra
mt=3, 22, 102, 103, 107
Calculated with the egnash code/2/.
mt=102
Calculated with the casthy code/10/.
References
1) Chiba, S. et al.: JAERI-M 92-027, p.35 (1992).
2) Yamamuro, N.: JAERI-M 90-006 (1990).
3) Kumabe, I. et al.: Nucl. Sci. Eng., 104, 280 (1990).
4) ENSDF: Evaluated Nuclear Structure Data File, BNL/NNDC.
5) Camarda H.S. et al. : Phys. Rev. C8, 1813 (1973).
6) Ohkubo M. : JAERI-M 5624 (1974).
7) Macklin R.L. et al. : LA-9200-MS (1982).
8) Mughabghab S.F. and Garber D.I. :"Neutron Cross Sections",
Vol. 2, Part B (1984).
9) Igarasi S. and Fukahori T.: JAREI 1321 (1991).
10) Raynal J. : IAEA-SMR-9/8 p.281 (1972).
11) Delaroche J.F. et al. : 1979 Knoxville Conf. 336 (1979).
12) Perey F.G.: Phys. Rev., 131, 745 (1963).
13) Aarthur, E.D. and Young, P.G.: LA-8626-MS (1980).
14) Lohr J.M. and Haeberli W.: Nucl. Phys., A232, 381 (1974).
15) Becchetti F.D. Jr. and Greenlees G.W.: "Polarization
Phenomena in Nucl. Reactions," Univ. Wisconsin Press, p.682
(1971).
16) Oyama, Y. et al.: JAERI-CONF 96-005, p70(1996).
17) Qaim,S.M. and Graca, C.: Nucl. Phys., A242, 317 (1975).
18) Voignier J. et al.: Nucl. Sci. Eng., 93, 43 (1986).
19) Kalbach C. : Phys. Rev. C37, 2350(1988).
20) Hida K.: JAERI-M 86-150 (1986) (in Japanese).
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