**45-Rh-103 Review**

Keiichi SHIBATA, JAERI Nuclear Data Center, December 2, 2002

1.  **Files**

BROND-2: Year of origin 1985

CENDL-3: Year of origin 1997

ENDF/B-VI: Year of origin 1971; capture cross section updated 1978;
Resonance parameters updated 1999.

JEF-2.2: Year of origin 1986; JEFF-3.0 taken from ENDF/B-VI.8

JENDL-3.2: Year of origin 1994; JENDL-3.3 taken from JENDL-3.2

2.  **Thermal and Resonance Region**

BROND-2: Resolved resonance parameters taken from BNL-325 (1981) below 2
keV; unresolved region between 2 and 200 keV.

CENDL-3: Resolved and unresolved resonance parameters taken from
JENDL-3.2.

ENDF/B-VI: Resolved resonance region below 4.1159 keV; unresolved
resonance region between 4.1159 and 40.146 keV.

JEF-2.2: Resolved resonance parameters taken from BNL-325 (1981) below
2.07 keV; unresolved resonance region between 2.07 and 39 keV.

JENDL-3.2: Resolved resonance region below 3.58 keV; unresolved
resonance region between 3.58 and 100 keV.

Thermal cross sections and resonance integral for Rh-103 (300K)

  -------------- -------------- -------------- -------------- --------------
                 Total (b)      Elastic (b)    Capture (b)    Cap. R.I. (b)

  JENDL-3.2      1.50014E+02    3.27570E+00    1.46739E+02    1.04292E+03

  ENDF/B-VI      1.49437E+02    4.37148E+00    1.45065E+02    1.03611E+03

  JEF-2.2        1.49774E+02    3.42979E+00    1.46345E+02    1.03472E+03

  CENDL-3        1.50014E+02    3.27570E+00    1.46739E+02    1.04292E+03

  BROND-2        1.49764E+02    3.42007E+00    1.46344E+02    1.03444E+03

  BNL-325                                      1452           110050
  -------------- -------------- -------------- -------------- --------------

**Recommendation**

In the resolved resonance region, the total and elastic scattering cross
sections in ENDF/B-VI seem to be in better agreement with measurements
than those in other libraries, although there is no preference for the
cross sections in the unresolved resonance region.

3.  **Fast Neutron Region**

    1.  **Methodology**

[BROND-2]{.underline}

The total and inelastic scattering cross sections were taken from
JENDL-1, while the (n,2n) cross section was taken from ENDF/B-V. As for
the capture cross section, the evaluation was based on experimental data
in the region from 200 keV to 800 keV; the ENDF/B-V data were adopted in
the region from 0.8 to 8 MeV; the DSD model calculations were adopted
above 8 MeV. No other reaction cross section is included. The elastic
scattering cross section was obtained by subtracting a sum of the
reaction cross sections from the total cross section.

[CENDL-3]{.underline}

Optical and statistical model calculations were performed. The direct
interaction was considered for the inelastic scattering by using DWBA.
The total cross section was taken from JENDL-3.2 in the energy region
from 200 keV to 401.9 keV, while the cross section was calculated with
the optical model above 401.9 keV. The (n,2n) cross section is based on
the measurements of Frehaut et al./Fr80/ and Veeser et al./Ve79/ The
library contains the cross sections for the (n,n'), (n,2n), (n,3n),
(n,np), (n,n), (n,), (n,p), (n,d), (n,t), (n,^3^He), and (n,) reactions
as well as the total and elastic scattering cross sections. The elastic
scattering cross section was obtained by subtracting a sum of the
reaction cross sections from the total cross section.

[ENDF/B-VI]{.underline}

Optical and statistical model calculations were performed. The capture
cross section is based on available experimental data. The (n,2n) cross
section followed the measurements of Bissem et al. /Bi70/ and Tewes et
al./Te60/ The capture cross sections were obtained by a least-squares
fit to experimental data. The library contains the total, elastic and
inelastic scattering, (n,2n), and capture cross sections.

[JEF-2.2]{.underline}

Optical and statistical model calculations were performed. No detailed
information is given in MF1. The library contains the cross sections for
the (n,n'), (n,2n), (n,), (n,p), (n,d), (n,t), (n,^3^He), and (n,)
reactions as well as the total and elastic scattering cross sections.

[JENDL-3.2]{.underline}

Optical and statistical model calculations were performed. The library
contains the cross sections for the (n,n'), (n,2n), (n,3n), (n,n),
(n,np), (n,nd), (n,nt), (n, ), (n,p), (n,d), (n,t), (n,^3^He), and (n,)
reactions as well as the total and elastic scattering cross sections.
The (n,2n) cross section is based on the measurements of Frehaut et
al./Fr80/ and Veeser et al./Ve79/ The (n,p) and (n, ) cross sections
were normalized to available experimental data at 14 MeV. The DSD
process was considered for the capture cross section in a
phenomenological way. The elastic scattering cross section was obtained
by subtracting a sum of reaction cross sections from the total cross
section.

2.  **MT=1**

JENDL-3.2 and CENDL-3 are in better agreement with measurements.

3.  **MT=2**

The JEF-2.2 data are constant values above 15 MeV. I cannot judge which
the best evaluation is.

4.  **MT=4**

The CENDL evaluation considered the direct interaction for the inelastic
scattering.

5.  **MT=16**

JENDL-3.2 and CENDL-3 are based on more recent measurements. JEF-2.2 is
much higher than available experimental data.

6.  **MT=102**

All evaluations reproduce available measurements up to several MeV.

7.  **MT=103**

JENDL-3.2 and CENDL-3 reproduce a measurement at 14 MeV.

8.  **MT=107**

JEF-2.2, JENDL-3.2 and CENDL-3 give cross sections. However, I cannot
judge which the best evaluation is, since experimental data are higher
or lower than the evaluations.

**Recommendation**

There is no big difference between the JENDL-3.2 and CENDL-3 data. I
would recommend CENDL-3, because it considered the direct interaction
for the inelastic scattering.

**References**

/Bi70/ H. Bissem et al.: EANDC(E) 1270, p.38 (1970).

/Fr80/ J. Frehaut et al.: Proc. Symp. Neutron Cross Sections from 10 to
50 MeV, BNL, p.399 (1980).

/Ve79/ L.R. Veeser et al.: Phys. Rev., C16, 1792 (1979).

/Te60/ H.A. Tewes et al.: UCRL-6038-T (1960).