45-Rh-103
45-Rh-103 JNDC EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.
DIST-MAY10 20091214
----JENDL-4.0 MATERIAL 4525
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
===========================================================
Resonance parameters in JENDL-3.3 were revised for JENDL-4.
===========================================================
===========================================================
JENDL-3.2 data were automatically transformed to JENDL-3.3.
Interpolation of spectra: 22 (unit base interpolation)
(3,251) deleted, T-matrix of (4,2) deleted, and others.
===========================================================
History
84-10 Evaluation for JENDL-2 was made by JNDC FPND W.G./1/
90-03 Modification for JENDL-3 was made/2/.
94-02 JENDL-3.2 was made by JNDC FPND W.G.
***** modified parts for JENDL-3.2 ********************
(2,151) Resolved and unresolved resonace parameters
(3,1), (3,2), (3,4), (3,51-91), (3,102), (3,251)
(4,2), (4,51-91)
New OMP was determined and renormalization of capture
cross section was made.
***********************************************************
10-03 JENDL-4.0 was made.
Resoloved resonance parameters were evaluated by K.Shibata.
Unresolved resonance parameters were evaluated by S.Kunieda.
The LSSF=1 was applied.
Compiled by S.Kunieda
***** modified parts for JENDL-4.0 ********************
(1,451) Updated.
(2,151) Updated.
(3,1) Re-calculated from partial cross sections.
(3,2) Calculated from URP in lower energy range.
(3,4) Re-calculated from partial cross sections.
(3,102) Calculated from URP in lower energy range.
***********************************************************
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 3.58 keV
Resonance parameters were mainly taken from JENDL-2.
Evaluation procedure of JENDL-2 is as follows:
Resonance energies and neutron widths were determined from the
experimental data of Ribon et al./3/ and Fricke and Carlson
/4/. Total spin J was taken from Haste and Thomas/5/ below
1.2 keV, Ribon et al. up to 2.63 keV, and Macklin and
Halperin/6/ above 2.65 keV. Radiation widths were evaluated
from the data of Ribon et al. and of Fricke and Carlson below
2.65 keV. Above 2.65 keV, radiation width was determined so
as to reproduce the capture areas of Macklin and Halperin/6/
corrected acocording to a corrigendum /7/. For levels whose
radiation width became negative, neutron width was calculated
from the capture areas of Macklin and Halperin, assuming the
radiation width of 0.16 eV/8/. Average radiation width of
0.160+-0.013 eV/8/ was assumed for the levels having no data
on radiation width. The effective scattering radius of 6.2 fm
was taken from Ref./8/.
For JENDL-3, total spin J of some resonances was tentative-
ly estimated with a random number method. Above 2.65 keV,
neutron widths were re-adjusted to reproduce the capture area
data of Mackin and Halperin/6/.
For JENDL-3.2, radiation width larger than 0.48 eV was
fixed to 0.48 eV and neutron width was re-adjusted so as to
reproduce the capture area data.
**************************************************************
In JENDL-4.0, the radiation width of 1.259-eV resonance was
changed to 139.6 meV in order to reproduce the thermal
capture cross section of 133.0+-0.93 b measured by Lee et
al./26/
**************************************************************
Unresolved resonance region : 3.58 keV - 100 keV
The parameters were adjusted to reproduce the capture cross
section calculated with CASTHY/9/. The effective scattering
radius was obtained from fitting to the calculated total cross
section at 100 keV.
Typical values of the parameters at 70 keV:
S0 = 0.440e-4, S1 = 4.100e-4, S2 = 0.530e-4, Sg = 71.8e-4,
Gg = 0.230 eV, R = 6.521 fm.
***************************************************************
For JENDL-4.0, the unresolved resonance parameters were
re-evaluated by the ASREP /27/ code so as to reproduce the
total and capture cross sections given in JENDL3.3 in the
energy region from 3.58 keV to 100 keV. The parameters should
be used only for self-shielding calculations.
***************************************************************
Thermal cross sections & resonance integrals at 300 K
----------------------------------------------------------
0.0253 eV res. integ. (*)
(barns) (barns)
----------------------------------------------------------
Total 1.36430E+02
Elastic 3.27510E+00
n,gamma 1.33155E+02 1.04460E+03
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
mf = 3 Neutron cross sections
Below 100 keV, resonance parameters were given.
Above 100 keV, the spherical optical and statistical model
calculation was performed with CASTHY, by taking account of
competing reactions, of which cross sections were calculated
with PEGASUS/10/ standing on a preequilibrium and multi-step
evaporation model.
The OMP's for neutron given in Table 1(a) were determined to
reproduce the measured total cross sections, and used in the
PEGASUS caculation. The OMP's for charged particles are as
follows:
proton = Perey/11/
alpha = Huizenga and Igo/12/
deuteron = Lohr and Haeberli/13/
helium-3 and triton = Becchetti and Greenlees/14/
Parameters for the composite level density formula of Gilbert
and Cameron/15/ were evaluated by Iijima et al./16/ More
extensive determination and modification were made in the
present work. Table 2 shows the level density parameters used
in the present calculation. Energy dependence of spin cut-off
parameter in the energy range below E-joint is due to Gruppelaar
/17/.
Another set of OMP of neutrons given in Table 1(b) was deter-
mined for JENDL-3.2 so as to reproduce better the total cross
section. This set of OMP was used in CASTHY calculation for
JENDL-3.2.
mt = 1 Total
Spherical optical model calculation with OMP in Table 1(b)
was adopted.
mt = 2 Elastic scattering
Calculated as (total - sum of partial cross sections).
mt = 4, 51 - 91 Inelastic scattering
Spherical optical and statistical model calculation with
CASTHY and OMP in Table 1(b) was adopted. The level scheme
was taken from Ref./18/.
no. energy(MeV) spin-parity
gr. 0.0 1/2 -
1 0.0397 7/2 +
2 0.0930 9/2 +
3 0.2950 3/2 -
4 0.3575 5/2 -
5 0.5368 5/2 +
6 0.6076 7/2 +
7 0.6501 7/2 +
8 0.6518 3/2 +
9 0.8036 3/2 -
10 0.8477 7/2 -
11 0.8804 5/2 -
12 0.9200 9/2 -
Levels above 0.96 MeV were assumed to be overlapping.
mt = 102 Capture
Spherical optical and statistical model calculation with
CASTHY and the OMP in Table 1(b) was adopted. Direct and
semi-direct capture cross sections were estimated according to
the procedure of Benzi and Reffo/19/ and normalized to 1
milli-barn at 14 MeV.
The gamma-ray strength function (6.67e-03) was adjusted to
reproduce the capture cross section of 295 milli-barns at 250
keV measured by Macklin et al./20,7/ the present results
are slightly larger than data of Wisshak et al./21/ at the
energies from 20 to 200 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 (= 111.5) was estimated by the
formula derived from Kikuchi-Kawai's formalism/22/ and level
density parameters.
Finally, the (n,p) and (n,alpha) cross sections were
normalized to the following values at 14.5 MeV:
(n,p) 17.00 mb (recommended by Forrest/23/)
(n,alpha) 11.00 mb (recommended by Forrest)
The (n,2n) cross section was determined by eye-guiding of the
data measured by Frehaut et al./24/ and Veeser et al./25/
mt = 251 mu-bar
Calculated with CASTHY.
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. For other reactions, isotropic distri-
butions 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 from overlapping levels and for
other neutron emitting reactions.
TABLE 1(A) NEUTRON OPTICAL POTENTIAL PARAMETERS
DEPTH (MEV) RADIUS(FM) DIFFUSENESS(FM)
---------------------- ------------ ---------------
V = 47.5 R0 = 5.972 A0 = 0.62
WS = 9.74 RS = 6.594 AS = 0.35
VSO= 7.0 RSO= 5.97 ASO= 0.62
THE FORM OF SURFACE ABSORPTION PART IS DER. WOODS-SAXON TYPE.
TABLE 1(B) NEUTRON OPTICAL POTENTIAL PARAMETERS FOR JENDL-3.2
DEPTH (MEV) RADIUS(FM) DIFFUSENESS(FM)
---------------------- ------------ ---------------
V = 48.81-0.4396E R0 = 1.234 A0 = 0.665
WS = 8.106+0.4862E RS = 1.421 AS = 0.377
VSO= 5.633 RSO= 1.241 ASO= 0.50
THE FORM OF SURFACE ABSORPTION PART IS DER. WOODS-SAXON TYPE.
RADIUS PARAMETERS ARE COEFFICIENTS OF A**(1/3) TERMS.
TABLE 2 LEVEL DENSITY PARAMETERS
NUCLIDE SYST A(1/MEV) T(MEV) C(1/MEV) EX(MEV) PAIRING
---------------------------------------------------------------
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
43-TC-101 1.675E+01 6.440E-01 6.361E+00 5.761E+00 9.400E-01
43-TC-102 1.761E+01 5.400E-01 1.217E+01 3.317E+00 0.0
44-RU-100 1.520E+01 7.200E-01 7.835E-01 8.078E+00 2.570E+00
44-RU-101 1.726E+01 6.700E-01 7.228E+00 6.836E+00 1.280E+00
44-RU-102 1.643E+01 6.550E-01 8.872E-01 7.106E+00 2.220E+00
44-RU-103 1.890E+01 6.480E-01 1.210E+01 7.110E+00 1.280E+00
45-RH-101 * 1.596E+01 6.476E-01 2.608E+00 5.832E+00 1.290E+00
45-RH-102 * 1.703E+01 6.452E-01 3.197E+01 4.966E+00 0.0
45-RH-103 1.570E+01 6.550E-01 4.298E+00 5.499E+00 9.400E-01
45-RH-104 1.714E+01 5.910E-01 1.771E+01 4.018E+00 0.0
---------------------------------------------------------------
syst: * = ldp's were determined from systematics.
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 6.375 for Rh-103 and 5.0 for Rh-104.
References
1) Aoki, T. et al.: Proc. Int. Conf. on Nuclear Data for Basic
and Applied Science, Santa Fe., Vol. 2, p.1627 (1985).
2) Kawai, M. et al.: J. Nucl. Sci. Technol., 29, 195 (1992).
3) Ribon, P., et al.: Nucl. Phys., A143, 130 (1970).
4) Fricke, M., Carlson, A.: GULF-RT-A-10739 (1971).
5) Haste, T.L., Thomas, B.W.: J. Phys. G, 1, 9, 981 (1975).
6) Macklin, R.L., Halperin, J.: Nucl. Sci. Eng., 73, 174 (1980).
7) Macklin, R.L. and Winters, R.R.: Nucl. Sci. Eng., 78, 110
(1981).
8) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I,
Part A", Academic Press (1981).
9) Igarasi, S. and Fukahori, T.: JAERI 1321 (1991).
10) Iijima, S. et al.: JAERI-M 87-025, p. 337 (1987).
11) Perey, F.G: Phys. Rev. 131, 745 (1963).
12) Huizenga, J.R. and Igo, G.: Nucl. Phys. 29, 462 (1962).
13) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974).
14) Becchetti, F.D., Jr. and Greenlees, G.W.: Polarization
Phenomena in Nuclear Reactions ((Eds) H.H. Barshall and
W. Haeberli), p. 682, the University of Wisconsin Press.
(1971).
15) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446
(1965).
16) Iijima, S., et al.: J. Nucl. Sci. Technol. 21, 10 (1984).
17) Gruppelaar, H.: ECN-13 (1977).
18) Matsumoto, J., et al.: JAERI-M 7734 (1978).
19) Benzi, V. and Reffo, G.: CCDN-NW/10 (1969).
20) Macklin, R.L., et al.: "Proc. Specialists' Meeting on
Neutron Cross Sections of Fission Products, Bologna 1979",
NEANDC(E) 209L, 103.
21) Wisshak, K. et al.: Phys. Rev., C42, 1731 (1990).
22) Kikuchi, K. and Kawai, M.: "Nuclear Matter and Nuclear
Reactions", North Holland (1968).
23) Forrest, R.A.: AERE-R 12419 (1986).
24) Frehaut, J., et al.: Symp. on Neutron Cross Sections from
10-50MeV, BNL, p.399 (1980)
25) Veeser,L.R., et al.: Phys. Rev., C16, 1792 (1977)
26) Lee, S., et al.: Nucl. Sci. Eng., 144, 94 (2003).
27) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999)
[in Japanese].