43-Tc- 99
43-Tc- 99 JNDC EVAL-Mar90 JNDC FP ND W.G., T.Nakagawa
DIST-MAY10 20090901
----JENDL-4.0 MATERIAL 4331
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
84-10 Evaluation for JENDL-2 was made by JNDC FPND W.G./1/.
90-03 Modification for JENDL-3 was made/2/.
93-11 JENDL-3.2 was made by JNDC FPND W.G./3/.
***** Modified parts for JENDL-3.2 ********************
(2,151) Resolved resonance parameters
***********************************************************
02-02 Modification was made by T.Nakagawa
***** Modified parts **************************************
(2,151) RRP and URP
(3,1),(3,2),(3,4),(3,22),(3,51-91),(3,102)
All of MF04 and MF05
***********************************************************
06-01 The neutron width of the negative energy resonance was
revised by K.Furutaka (jaea).
09-08 The total cross section was re-calculated from partial cross
sections.
Compiled by K.Shibata (jaea) for JENDL-4.0.
MF = 1 General information
MT=451 Comments and dictionary
MF = 2 Resonance parameters
MT=151 Resolved and unresolved resonance parameters
Resolved resonance region (MLBW formula) : below 6.0 keV
All the resolved resonance parameters were brought
unmodified from JENDL-3.3 except for the negative-energy one
: in JENDL-3.3/4/, resonance parameters obtained by
Gunsing et al./5/ were adopted. They analyzed their
transmission data with REFIT code, and obtaind the
parameters up to 10 keV. The upper boundary of the resolved
resonance region was set to 6 keV in this file as in
JENDL-3.3, because the capture cross section calculated from
their parameters were smaller than experimental data above
the energy. Neutron width of the negative-energy resonance
was slightly adjusted so as to reproduce the value of
capture cross section for thermal neutrons adopted in this
file. The adopted value is 23.6 b, which is the weighted
average of the cross sections reported by Molnar et al.6/
and Furutaka et al./7/ deduced from emission cross
sections of 540- and 591-keV decay gamma rays in Ru-100
using the recent gamma-ray emission probabilities for the
gamma rays/8/, and the corresponding values reported by
Harada et al./9/ recalculated with the new emission
probabilities.
The scattering radius of 6.7 fm was adopted.
Unresolved resonance region : 6.0 keV - 100 keV
Unresolved resonance parameters were adjusted with ASREP/10/
to reproduce the capture and total cross sections calculated
with CASTHY. The parameters should be used only for self-
shileding calculation.
Thermal cross sections and resonance integrals at 300 K
----------------------------------------------------------
0.0253 eV res. integ. (*)
(barns) (barns)
----------------------------------------------------------
Total 2.8261E+01
Elastic 4.6567E+00
n,gamma 2.3605E+01 3.2384E+02
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
MF = 3 Neutron cross sections
Below 6 keV, resonance parameters were given.
Above 6 keV, the spherical optical and statistical model
calculation was performed with CASTHY/11/, by taking account of
competing reactions, of which cross sections were calculated
with PEGASUS/12/ standing on a preequilibrium and multi-step
evaporation model. The OMP's for neutron given in Table 1 were
determined to reproduce the total cross section measured by
Foster and Glasgow/13/ in the MeV region, and total cross
section of about 8 - 9 b in the 10-100 keV region. The OMP's
for charged particles are as follows:
Proton = Perey/14/
Alpha = Huizenga and Igo/15/
Deuteron = Lohr and Haeberli/16/
Helium-3 and triton = Becchetti and Greenlees/17/
Parameters for the composite level density formula of Gilbert
and Cameron/18/ were evaluated by Iijima et al./19/ More
extensive determination and modification were made in the
previous work/2/. Table 2 shows the level density parameters
used in the calculation. Energy dependence of spin cut-off
parameter in the energy range below E-joint is due to Gruppelaar
/20/.
MT = 1 Total
Spherical optical model calculation was adopted.
MT = 2 Elastic scattering
Calculated as (total - sum of partial cross sections).
MT = 4, 51 - 91 Inelastic scattering
The level scheme was taken from Ref./21/
No. Energy(MeV) Spin-parity
GR. 0.0 9/2 +
1 0.1405 7/2 + *
2 0.1427 1/2 -
3 0.1811 5/2 + *
4 0.5091 3/2 -
5 0.5344 3/2 -
6 0.5369 5/2 +
7 0.6125 5/2 - *
8 0.6254 9/2 + *
9 0.6715 3/2 -
10 0.7198 7/2 + *
11 0.7267 11/2 + *
12 0.7617 5/2 + *
13 0.7619 13/2 + *
14 0.9206 1/2 +
15 0.9861 7/2 - *
16 1.0041 3/2 -
Levels above 1.0175 MeV were assumed to be overlapping.
The compound inelastic scattering was calculated with CASTHY.
For the levels with "*", direct inelastic scattering was
calculated with DWUCK /22,23/. Deformation parameters were
based on the recommendation by Raman et al./24/
MT = 102 Capture
Spherical optical and statistical model calculation with
CASTHY was adopted. Direct and semi-direct capture cross
sections were estimated according to the procedure of Benzi
and Reffo/25/ and normalized to 9 mb at 14.7 MeV /26/.
The gamma-ray strength function (8.01E-03) was adjusted to
reproduce the capture cross section of 630 mb at 50 keV.
MT = 16 (n,2n) Cross Section
MT = 17 (n,3n) Cross Section
MT = 22 (n,n'a) Cross Section
MT = 28 (n,n'p) Cross Section
MT = 32 (n,n'd) Cross Section
MT = 33 (n,n't) Cross Section
MT =103 (n,p) Cross Section
MT =104 (n,d) Cross Section
MT =105 (n,t) Cross Section
MT =106 (n,He3) Cross Section
MT =107 (n,alpha) Cross Section
These reaction cross sections were calculated with the
preequilibrium and multi-step evaporation model code PEGASUS.
The Kalbach's constant K (= 101.5) was estimated by the
formula derived from Kikuchi-Kawai's formalism/27/ and level
density parameters.
Finally, the (n,2n) and (n,p) cross sections were normalized
to the following values at 14.5 MeV:
(n,2n) 1230.00 mb (recommended by Bychkov et al./28/)
(n,p) 14.00 mb (recommended by Forrest/29/)
The (n,alpha) and (n,n'alpha) cross section was normalized to
the data of Ikdeda et al. /30/
MF = 4 Angular Distributions of Secondary Neutrons
Legendre polynomial coefficients for angular distributions are
given in the center-of-mass system for MT=2 and discrete inelas-
tic levels, and in the laboratory system for MT=91. They were
calculated with CASTHY. Those of direct inelastic scttering
were calculated with DWUCK, and added to the rusults of CASTHY
calculation.
For other reactions, isotropic distributions in the laboratory
system were assumed.
MF = 5 Energy Distributions of Secondary Neutrons
Energy distributions of secondary neutrons were calculated with
PEGASUS for inelastic scattering to overlapping levels and for
other neutron emitting reactions.
Interpolation of 22 (unit base interpolation) was adopted.
Table 1 Neutron Optical Potential Parameters
Depth (MeV) Radius(fm) Diffuseness(fm)
---------------------- ------------ ---------------
V = 45.5-0.48*En r0 = 1.350 a0 = 0.60
Ws = 6.79+0.83*En rs = 1.330 as = 0.40
Vso= 7.0 rso= 1.350 aso= 0.60
The form of surface absorption part is der. Woods-Saxon type.
Table 2 Level Density Parameters
Nuclide a(1/MeV) T(MeV) C(1/MeV) EX(MeV) Pairing
---------------------------------------------------------------
41-Nb- 95 1.277E+01 7.500E-01 2.121E+00 5.782E+00 1.120E+00
41-Nb- 96 1.331E+01 5.880E-01 3.406E+00 2.530E+00 0.0
41-Nb- 97 1.337E+01 6.710E-01 9.771E-01 5.026E+00 1.290E+00
41-Nb- 98 1.380E+01 5.110E-01 2.350E+00 1.731E+00 0.0
42-Mo- 96 1.403E+01 7.410E-01 6.991E-01 7.645E+00 2.400E+00
42-Mo- 97 1.517E+01 6.800E-01 2.769E+00 6.036E+00 1.280E+00
42-Mo- 98 1.594E+01 6.900E-01 7.358E-01 7.888E+00 2.570E+00
42-Mo- 99 1.774E+01 6.200E-01 4.294E+00 6.058E+00 1.280E+00
43-Tc- 97 1.600E+01 6.700E-01 4.756E+00 6.089E+00 1.120E+00
43-Tc- 98 1.659E+01 6.120E-01 1.776E+01 4.176E+00 0.0
43-Tc- 99 1.600E+01 6.550E-01 2.973E+00 5.984E+00 1.290E+00
43-Tc-100 1.637E+01 5.850E-01 1.189E+01 3.635E+00 0.0
---------------------------------------------------------------
Spin cutoff parameters were calculated as 0.146*SQRT(a)*A**(2/3).
In the CASTHY calculation, spin cutoff factors at 0 MeV were
assumed to be 7.899 for Tc- 99 and 5.0 for Tc-100.
References
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[in Japanese]
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(1987)
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Reactions", North Holland (1968).
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