41-Nb- 93
41-NB- 93 NAIG EVAL-NOV88 M.KAWAI, N.YAMAMURO
DIST-MAR02 REV3-FEB02 20020215
----JENDL-3.3 MATERIAL 4125
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
82-10 Evaluation of resonance parameters for JENDL-2 was made
by Kawai.
88-10 Evaluation was performed for JENDL-3.
88-10 Compiled by K.Shibata (JAERI).
94-02 JENDL-3.2
Resonance parameters modified by M.Kawai(Toshiba).
Gamma-ray production data by S.Igarasi(NEDAC).
Other data were adopted from JENDL fusion file.
Compiled by T.Nakagawa
***** Modified parts for JENDL-3.2 ********************
(2,151) resolved resonance parameters modified
(3,1), (3,2), (3,4), (3,51-91) from JENDL fusion file
(4,16-91) taken from JENDL fusion file
(5,16-91) taken from JENDL fusion file
(12,102) below 100 keV
(15,102) below 100 keV
***********************************************************
-------------------------------------------------------------
JENDL fusion file /1/ (as of Feb. 1994)
Evaluated by B.Yu(CIAE) and S.Chiba (NDC/JAERI)
Compiled by S.Chiba.
- Cross sections were mainly taken from JENDL-3.1 except
for the (n,2n) and continuum inelastic scattering cross
sections which were taken from the SINCROS-II/2/
calculation. Interpolation scheme of the discrete
inelastic scattering cross sections was changed from 3
to 2. The total cross section at 10 and 15 keV, which
is the background cross section, were set to 0.0.
- Energy distributions were replaced with the SINCROS-II
calculation.
- MF=6 was made by the M15TOB program/1/. The precom-
und to compound ratio was taken from output of the
SINCROS-II calculation. Kalbach's systematics/3/ was
adopted for DDX.
- 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/.
Modefied by T.Fukahori (NDC/JAERI) on Aug. 13, 1996
- Total cross section between 0.5 and 4 MeV is modefied so
as to reproduce the experimental data L. Green et al./23/
A.B. Smith et al./24/.
- Newly evaluated value of (n,alpha) reaction cross section
considered old version of JENDL fusion file, FENDL-1 and
the experimental data measured by A. Mannan et al./25/
and R. Woelfle et al./26/ is replaced old one.
-------------------------------------------------------------
2001-08 JENDL-3.3
Evaluated by Y. Watanabe (Kyushu Univ.)
Compiled by Y. Watanabe and K. Shibata
Gamma-ray energy distributions for radiative capture
(MT=102) were modified. Other data were adopted from
JENDL-3.2 and JENDL-fusion file.
***** modified parts for JENDL-3.3 ********************
(6,16-91) taken from the JENDL fusion file
(6,202,203,204,207) taken from the JENDL fusion file
(12,102),(15,102) newly evaluated above 3 MeV
***********************************************************
- Cross sections were taken from the JENDL-3.2.
- Energy-angle distributions (MF=6) were taken from the
JENDL fusion file.
- For the (n,gamma) energy distribution, semi-direct
component calculated using the GNASH code/27/ was added
to the statistical component taken from JENDL-3.2
after appropriate renomalization for incident energies
above 3 MeV.
MF=1 General information
MT=451 Descriptive data and dictionary
MF=2 Resonance parameters
MT=151
Resolved resonances: 1.0e-5 eV - 7 keV
Parameters in JENDL-3.1 were taken from JENDL-2 by modifying
J values. The JENDL-2 parameters were evaluated on the basis
of following measurements:
transmission by Garg et al./5/, Poittevin et al./6/
and Iliescu et al./7/
scattering by Iliescu et al./7/
capture by Macklin /8/, Lopez et al./9/ and
Iliescu et al. /7/
J values determined by Haste et al. /10/ were adopted.
average radiative width was assumed to be 0.172 eV (0.212 eV
for doublet), and Scattering radius to be 7.10 fm. The J
values of resonances without known j values were randomly
assigned.
For JENDL-3.2, re-assignment of J and modification of neutron
and radiative widths were made to reproduce the measured
capture area data/8/.
Unresolved resonances: 7 keV - 100 keV
Determined with the asrep code/11/ so as to reproduce
the evaluated sig-c and sig-t up to 100 keV.
Typical parameters at 70 keV:
s0= 0.4e-4, s1=6.68e-4, d-obs=96.0 ev, r=6.477 fm,
radiative width= 0.172 eV
Calculated 2200-m/s cross sections and res. integrals
2200-m/s res. integ.
elastic 6.319 b -
capture 1.149 b 9.445 b
total 7.468 b -
MF=3 Neutron cross sections
MT=1 Total
Below 100 keV : background cross sections given.
100 keV to 20 MeV: spline-function fitting to the
experimental data/12/.
MT=2 Elastic scattering
(total) - (reaction cross section)
MT=4,51-62,91 Inelastic scattering
The inelastic scattering cross sections to discrete levels
were calculated with the statistical-model code casthy
/13/, considering level fluctuation, using modified
walter-guss potential parameters for neutrons. The
components of the direct process were added to the levels
of mt=53, 54, 56, 57, 58, 60 by using the DWUCK code /14/.
The cross section to continuum was calculated with the the
GNASH code /15/ considering pre-equilibrium. The
modification made for JENDL fusion file was also adopted
to JENDL-3.2.
The level scheme is given as follows:
no. energy(mev) spin-parity
g.s 0.0 9/2 +
1. 0.0304 1/2 -
2. 0.6860 3/2 -
3. 0.7440 7/2 +
4. 0.8087 5/2 +
5. 0.8101 3/2 -
6. 0.9499 13/2 +
7. 0.9791 11/2 +
8. 1.0826 9/2 +
9. 1.2900 3/2 -
10. 1.2974 9/2 +
11. 1.3156 5/2 +
12. 1.3351 17/2 +
Levels above 1.34 mev were assumed to be overlapping.
Optical-model parameters are as follows:
V=52.56-0.30*En, Ws=3.233+0.271*En, Vso=6.004-0.015*En
Vsym=-16.5 , Wi=-0.963+0.153*en, Wso=0.291-0.018*En
r0=1.229 , rs=1.282 , ri=1.42, rso=1.103
a0=0.688 , b=0.512 , ai=0.509, aso=0.56
The level density parameters for GNASH and CASTHY
calculations are as follows:
a ex t ds gamma-g
(1/mev) (mev) (mev) (ev) (ev)
Nb-94 14.4 4.059 0.719 30.0 0.052
Nb-93 13.0 5.884 0.834 - 0.170
Nb-92 11.5 3.254 0.790 - 0.170
Nb-91 11.0 5.461 0.895 - 0.170
Zr-93 13.7 5.923 0.781 - 0.140
Zr-92 11.9 6.284 0.858 - 0.140
Y-90 11.1 1.441 0.721 1210. 0.130
Y-89 10.7 2.946 0.762 - 0.130
MT=16 (n,2n)
Based on the experimental data/16,17/.
MT=17,22,28,103,104,107 (n,3n),(n,n'a),(n,n'p),(n,p)
(n,d) and (n,a) cross sections
calculated with gnash/15/.
optical potential parameters for proton, alpha-particle
and deuteron were taken from the works of Perey/18/,
Lemos/19/ and Lohr and Haeverli/20/, respectively.
MT=102 Radiative capture cross section
1.0e-5 eV to 100 keV: resonance parameters given.
100 kev to 20 MeV: calculated with the CASTHY code/13/.
t-gamma=0.0109; determined so as to reproduce
sig-c=107mb at 100 keV, measured by Reffo et al./21/
MF=4 Angular distributions of secondary neutrons
MT=2,51-62
Calculated with CASTHY for equilibrium process. The
components of the direct process were added to the levels
of MT=53,54,56,57,58,60 by using the DWUCK code /14/.
MF=6 Energy and angle distributions of secondary
neutron, proton, deuteron, and alpha particle
MT=16, 17, 22, 28, 91, 202, 203, 204, 207
Taken from JENDL fusion file.
MF=12 Photon production multiplicities
MT=16,17,22,28,52-62,91,103,104,107
Calculated with GNASH/15/.
MT=102
From energy balance. Semi-direct component was taken
into account above 3 MeV.
MF=14 Photon angular distributions
MT=16,17,22,28,52-62,91,102,103,104,107
Assumed to be isotropic.
MF=15 Photon energy distributions
MT=16,17,22,28,91,103,104,107
Calculated with GNASH/15/.
MT=102
Below 3 MeV, calculated with CASTHY, referring to
the compilation of gamma-ray spectra for thermal neutron
by Lone et al./22/ Primary transitions were taken into
account at 1.0e-5, 2.53e-2, 1.0e+1, 1.0e+3, 3.0e+4 and
1.0e+5 eV. More than 3 MeV, semi-direct component
calculated by GNASH code/27/ was included. The component
was normalized to the experimental data of
Rigaud et al./28/.
References
1) Chiba, S. et al.: JAERI-M 92-027, p.35 (1992).
2) Yamamuro, N.: JAERI-M 90-006 (1990).
3) Kalbach, C.: Phys. Rev. C, 37, 2350 (1988).
4) ENSDF: Evaluated nuclear structure data file, BNL/NNDC.
5) Garg, J.B. et al.: Phys. Rev. B137, 547 (1965).
6) Poittevin, G.Le. et al.: Nucl. Phys. 70, 497 (1965).
7) Iliescu, N. et al.: Nucl. Phys. 72, 298 (1965).
8) Macklin, R.L.: Nucl. Sci. Eng. 59, 12 (1976).
9) Lopez, W.M. et al.: Nucl. Phys. A93, 340 (1967).
10) Haste, T.J. and Thomas B.W.: J. Phys. G1, 967 (1975).
11) Kikuchi, Y.: unpublished.
12) Poenitz, W.P. and Whalen, J.F.: ANL/NDM-80 (1983).
13) Igarasi, S. and Fukahori, T.: JAERI 1321 (1991).
14) Kunz, P.D.: Univ. Colorado (1974).
15) Young, P.G. and Arthur, E.D.: LA-6947 (1977).
16) Frehaut, J. et al.: Proc. Symp. Neutron Cross-sections from 10
to 50 MeV, BNL, 1980, p. 399 (1980).
17) Veeser, L.R. et al.: Phys. Rev. C, 16, 1792 (1977).
18) Perey, F.G.: Phys. Rev. 131, 745 (1963).
19) Lemos, O.F.: "Diffusion elastique de particules alpha de 21 a
29.6 mev sur des noyaux de la region ti-zn", Orsay Report,
Series A., No. 136, (1972).
20) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974).
21) Reffo, G. et al.: Nucl. Sci. Eng., 80, 630 (1982).
22) Lone, M.A., Leavitt, R.A. and Harrison D.A.: At. Data and
Nucl. Data Tables, 26, 511 (1981).
23) Green, L., et al.: WAPD-TM-1073 (1973).
24) Smith, A.B., et al.: ANL-NDM-70 (1982).
25) Mannan, A., et al.: Phys. Rev. C, 38, 630 (1988).
26) Woelfle, R., et al.: Appl. Rad. Isotopes 39, 407 (1988).
27) Young, P.G., et al.: LA-12343-MS (1992).
28) Rigaud, F., et al.: Nucl. Phys. A173, 551 (1971).