44-Ru-100
44-Ru-100 JNDC EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.
DIST-MAY10 20091208
----JENDL-4.0 MATERIAL 4437
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
===========================================================
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/.
09-12 JENDL-4.0.
Compiled by A.Ichihara (jaea/ndc).
***** modified parts for JENDL-4.0 *******************
(2,151) Resolved resonance parameters were revised
by T.Nakagawa.
**********************************************************
mf = 1 General information
mt=451 Comments and dictionary
mf = 2 Resonance parameters
mt=151 Resolved and unresolved resonance parameters
Resolved resonance region (MLBW; below 11.89 keV)
The data of JENDL-3.3 was adopted, and capture width of a
negative resonance was adjusted to repruduce the measured
thermal cross section of 5.8 +- 0.4/3/
** comments to JENDL-3.3 **
Resonance parameters were taken from JENDL-2 except for those
of negative and hypothetical resonances, angular momentum for
some levels and scattering radius.
For JENDL-2, the 228.5-eV resonance was adopted from
Priesmeyer and Jung/4/. Resonances above 2679.7 eV were
mainly based on the experimental data of Macklin and Halperin
/5/. Resonances at 120 eV and between 336 and 2497 eV were
hypothetical levels generated by assuming S0=0.43e-4, D0=340
eV, S1=4.1e-4, D1=110 eV. The average radiation width of
0.124+-0.017 eV was deduced and adopted to the levels whose
radiation width was unknown. Two negative resonances were
added, and parameters of the 120-eV level were adjusted so as
to reproduce the capture cross section of 5.0+-0.6 barns at
0.0253 eV and the capture resonance integral of 11.2+-1.1
barns/6/.
For JENDL-3, the reduced neutron width was decreased from
43 meV to 23 meV. Scattering radius was changed to 6.1 fm
according to the systematics of measured values. Number of
negative resonances was reduced to one and its parameters were
reevaluated. Neutron orbital angular momentum l of some
resonances was estimated with a method of Bollinger and Thomas
/7/.
Unresolved resonance region : 11.89 keV - 100 keV
Unresolved resonance parameters were adopted from JENDL-2.
The neutron strength functions, S0, S1 and S2 were calculated
with optical model code CASTHY/8/. The observed level spacing
was determined to reproduce the capture cross section
calculated with CASTHY. 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 = 0.450e-4, S1 = 6.500e-4, S2 = 0.530e-4, Sg = 3.91e-4,
Gg = 0.125 eV, R = 4.971 fm.
The unresolved resonance parameters were calculated using
the ASREP code/9/.
The parameters should be used only for self-shielding
calculation.
Thermal cross sections and resonance integrals at 300K (b)
-------------------------------------------------------
0.0253 eV reson. integ.(*)
-------------------------------------------------------
total 12.341
elastic 6.498
capture 5.842 11.5
-------------------------------------------------------
(*) In the energy range 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 were
determined to reproduce a systematic trend of the total cross
section by changing rso of Iijima-Kawai potential/11/. The
OMP's for charged particles are as follows:
proton = Perey/12/
alpha = Huizenga and Igo/13/
deuteron = Lohr and Haeberli/14/
helium-3 and triton = Becchetti and Greenlees/15/
Parameters for the composite level density formula of Gilbert
and Cameron/16/ were evaluated by Iijima et al./17/ 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
/18/.
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
Spherical optical and statistical model calculation was
adopted. The level scheme was taken from Ref./19/.
no. energy(MeV) spin-parity dwba cal.
gr. 0.0 0 +
1 0.5396 2 + *
2 1.1304 0 +
3 1.2265 4 +
4 1.3621 2 +
5 1.7407 0 +
6 1.8653 1 +
7 1.8812 3 +
8 2.0517 0 +
9 2.0639 3 - *
10 2.0777 6 +
11 2.0993 2 -
12 2.1673 2 -
13 2.2406 1 +
14 2.3872 0 +
15 2.4694 2 -
16 2.5168 2 +
Levels above 2.613 MeV were assumed to be overlapping.
For the levels with an asterisk, the contribution of direct
inelastic scattering cross sections was calculated by the
DWUCK-4 code/20/. Deformation parameters (beta2 = 0.2172 and
beta3 = 0.116) were based on the data compiled by Raman et
al./21/ and Spear/22/, respectively.
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/23/ and normalized to 1 milli-barn at 14 MeV.
The gamma-ray strength function (3.79e-04) was adjusted to
reproduce the capture cross section of 120 milli-barns at 70
keV measured by Macklin et al./24,25/
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 =103 (n,p) cross section
mt =104 (n,d) cross section
mt =105 (n,t) 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 (= 89.2) was estimated by the
formula derived from Kikuchi-Kawai's formalism/26/ 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) 15.00 mb (recommended by Forrest/27/)
(n,alpha) 8.70 mb (systematics of Forrest/27/)
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. Contribution of direct inelastic
scattering was calculated with DWUCK-4. 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.
TABLE 1 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 2 LEVEL DENSITY PARAMETERS
NUCLIDE A(1/MEV) T(MEV) C(1/MEV) EX(MEV) PAIRING
---------------------------------------------------------------
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
44-RU- 98 1.382E+01 7.400E-01 6.070E-01 7.507E+00 2.400E+00
44-RU- 99 1.650E+01 6.570E-01 4.016E+00 6.235E+00 1.280E+00
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
---------------------------------------------------------------
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 4.062 for Ru-100 and 14.30 for Ru-101.
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.: Proc. Int. Conf. on Nuclear Data for Science
and Technology, Mito, p. 569 (1988).
3) J.Halperin et al.: ORNL 3832, p.4 (1965).
4) H.G.Priesmeyer, H.H.Jung: Atomkernenergie, 19, 111 (1972).
5) R.L.Macklin, J.Halperin: Nucl. Sci. Eng., 73, 174 (1980).
6) S.F.Mughabghab et al.: "Neutron Cross Sections, Vol. I,
Part A", Academic Press (1981).
7) L.M.Bollinger, G.E.Thomas: Phys. Rev., 171,1293 (1968).
8) Igarasi, S.: J. Nucl. Sci. Technol., 12, 67 (1975).
9) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999)
[in Japanese].
10) Iijima, S. et al.: JAERI-M 87-025, p. 337 (1987).
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(1983).
12) Perey, F.G: Phys. Rev. 131, 745 (1963).
13) Huizenga, J.R. and Igo, G.: Nucl. Phys. 29, 462 (1962).
14) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974).
15) 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).
16) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446
(1965).
17) Iijima, S., et al.: J. Nucl. Sci. Technol. 21, 10 (1984).
18) Gruppelaar, H.: ECN-13 (1977).
19) Matsumoto, J.: private communication (1981).
20) Kunz, P.D.: private communication.
21) Raman, S., et al.: Atom. Data and Nucl. Data Tables 36, 1
(1987)
22) Spear, R.H.: Atom. Data and Nucl. Data Table, 42, 55 (1989).
23) Benzi, V. and Reffo, G.: CCDN-NW/10 (1969).
24) Macklin, R.L., et al.: Proc. Specialists' Meeting on Neutron
Cross Sections of Fission Products, Bologna 1979, NEANDC(E)
209L, 103.
25) Macklin, R.L., Winters, R.R.: Nucl. Sci. Eng., 78, 110(1981).
26) Kikuchi, K. and Kawai, M.: "Nuclear Matter and Nuclear
Reactions", North Holland (1968).
27) Forrest, R.A.: AERE-R 12419 (1986).