68-ER-170 TIT EVAL-SEP00 A.K.M. HARUN-AR-RASHID+
DIST-MAR02 20020205
----JENDL-3.3 MATERIAL 6849
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
2000-09 Evaluation was performed by A.K.M.Harun-ar-Rashid (tit),
M.Igashira (tit), T.Ohsaki (tit), and K.Shibata (jaeri).
2001-02 Compiled by K.Shibata (jaeri).
mf=1 General information
mt=451 Descriptive data and dictionary
mf=2 Resonance parameters
mt=151 Resolved resonances
Resonance range (1.0e-05 to 3.00e+03 eV).
Resolved resonance parameters from Ref.1 (Ehi=3000.0 eV).
The bound level at -336.0 eV has Gamma-n = 13.0645 eV and
Gamma-gamma = 0.082 eV. This choice gives the desired
value for the thermal capture cross section, 5.8+-0.3 b.
Values of gamma-gamma not given in Ref.1 are set to 0.092 eV.
21 resonances [L=1] did not have values given for "J", 10 are
assigned to J= 0.5 and the remaining 11 to J= 1.5 by random
method. The value for the scattering radius is 8.0 fm, taken
from Ref.2 with small change with in the given error, so as
to produce the close value of the thermal neutron scattering
cross section recommended by Mughabghab [2].
Highest energy resonance included is 2977.8 eV.
No background cross sections are given.
Calculated 2200-m/s cross sections and res. integrals
2200-m/s res. integ.
elastic 11.967 b -
capture 5.776 b 45.211 b
total 17.743 b -
mf=3 Neutron cross sections
mt= 1 Total cross section
Spherical optical model calculation was made by using
casthy code [3]. Parameters are as follows,
V = 48.2-0.25*E-16.0*(N-Z)/A , r0=1.18, a0=0.63
Ws = 7.84-0.51*E , rs=1.29, as=0.63
Vso= 6.0 , rso=1.26, aso=0.63
(energies in MeV, lengths in fm).
mt= 2 Elastic scattering cross section
The cross sections were obtained by subtracting a sum of
reaction cross sections from the total cross sections.
mt= 4,51,52,.,64,91 Inelastic scattering cross sections
Calculated by using egnash code [4,5].
The direct-process component was considered for mt=51
from dwba calculation by dwucky code. [4,6]
The level scheme is given as follows:
no energy(MeV) spin parity
g.s 0.00000 0.0 +
1 0.07870 2.0 +
2 0.26020 4.0 +
3 0.54080 6.0 +
4 0.89100 0.0 +
5 0.91230 8.0 +
6 0.93400 2.0 +
7 0.95990 2.0 +
8 1.01040 3.0 +
9 1.10330 4.0 +
10 1.12720 4.0 +
11 1.21740 3.0 +
12 1.23620 5.0 +
13 1.26640 1.0 -
14 1.26860 4.0 -
Levels above 1.300 MeV are assumed to be overlapping
mt= 16,17,22,28,32,103,104,105,107
(n,2n), (n,3n), (n,n'a), (n,n'p), (n,n'd)
(n,p), (n,d), (n,t), (n,a)
Calculated using egnash [4,5].
mt=102 Capture cross secton
The capture cross section is based on the statistical model
calculations. The measured data of Refs. 7 and 8 were taken
into account. The direct and semidirect capture cross
sections were added above 2 MeV by using the quick gnash code
[5,9].
mf=4 Angular distributions of secondary neutrons
mt=2
Calculated with the casthy code.
mt=16,17,22,28,32,
Assumed to be isotropic in the laboratory system.
mt=51,---,64,91
Calculated with the casthy code.
For mt=51, the dwba component was taken into account.
mf=5 Energy distributions of secondary neutrons
mt=16,17,22,28,32,91
Calculated with the egnash code.
mf=12 Photon production multiplicities
mt=16,17,22,28,51-64,91,102,103,104,107
Calculated with the egnash code.
mf=14 Photon angular distributions
mt=16,17,22,28,51-64,91,102,103,104,107
Assumed to be isotropic.
mf=15 Photon energy distributions
mt=16,17,22,28,91,102,103,104,107
Calculated with the egnash code.
References
1. Landolt-Boernstein New Series I/16B (Aug 1998).
2. S. F. Mughabghab: "Neutron Cross Sections: Vol. 1,
Neutron Resonance Parameters and Thermal Cross Sections,
Part B: Z=61-100," Academic press (1984).
3. S. Igarasi, T. Fukahori: JAERI 1321 (1991).
4. N. Yamamuro: JAERI-M 90-006 (1990).
5. P.G. Young et al.: LA-12343-MS, UC-413 (1992).
6. P.D. Kunz: Program DWUCK4, Computational Nuclear
Physics 2: Nuclear Reaction; edited by K. Langanke et al.,
published by Springer-Verlag (1992).
7. D.C. Stupegia et al.: JNE, 22, 267 (1968) .
8. M. Igashira et al.: Private communication (2002).
9. N. Yamano: Private communication.