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Isomeric ratios 

were calculated for $^{121}$Te and $^{133}$Ba from the measured partial and total (n, γ ) cross sections. The present results at kT =25 keV are 0.126 ± 0.012 and 0.090 ± 0.009, respec- tively. These results are compatible with the thermal values at kT = 25 meV, which are 0.145 ± 0.026 for $^{121}$Te and 0.071 for $^{133}$Ba [35, 36]. 

## VI. MAXWELLIAN AVERAGED CROSS SECTIONS 

In an astrophysical environment with temperature T , interacting particles are quickly thermalized by collisions in the stellar plasma, and the neutron energy distribution can be described by a Maxwell-Boltzmann spectrum: 

The experimental neutron spectrum of the $^{7}$Li( p, n ) $^{7}$Be reaction simulates the energy dependence of the flux v · Φ ∼ E$_{n}$ · e − E$_{n}$/kT with kT =25.0 ± 0.5 keV almost perfectly [21]. However, the cutoff at E$_{n}$ = 106 keV and small deviations from the shape of the ideal Maxwellian spectrum require a correction of the measured cross sec- tion 〈 σ$_{exp}$ 〉 for obtaining a true Maxwellian average, 〈 σ 〉 25 keV . This correction is determined by means of the energy-dependent cross sections from data libraries. 

## B. Evaluated cross sections from data libraries 

The corrections for the spectrum differences as well as the extrapolations of the MACS to lower and higher values of kT were determined with the evaluated energy- dependent cross sections, σ (E$_{n}$), from the data libraries provided by the online database JANIS 3.0 (”Java-based Nuclear Information Software”, www.nea.fr/janis/) [37]. 

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## F. Isomeric ratios 

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## A. General remarks 

The libraries used were the ”Joint Evaluated Fis- sion and Fusion General Purpose File” ( JEFF 3.0A and JEFF 3.1 , www.nea.fr/html/dbdata/ JEFF/ ), the ”Japanese Evaluated Nuclear Data Library” ( JENDL 3.3 [38], wwwndc.tokai-sc.jaea.go.jp/jendl/), and the ”Evaluated Nuclear Data File” ( ENDF-B/VII.0 [39], www.nndc.bnl.gov/), which are partially based on experimental resonance parameters. 

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For the investigated cases, the most recent data for σ (E$_{n}$) are provided by ENDF-B/VII.0 , which makes use of resonance parameters from the latest evaluation [36]. The differences between the four data libraries with respect to the resolved resonance region (RRR) are sum- marized in Table XI. Table XII shows that the contribu- tions of the RRR to the respective Maxwellian averaged cross sections for kT =5-100 keV are almost negligible, ex- cept for the lower temperatures in $^{130}$Ba, where the RRR reaches up to about 3 keV. In all libraries, the ( n, γ ) cross sections in the unresolved resonance region (URR) were obtained by Hauser-Feshbach (HF) calculations. Since this region contributes the most important part to the extrapolation towards the higher temperatures of the p - process, it is discussed in more detail. 

The Hauser-Feshbach calculations in the JENDL-3.3 evaluations were performed with the statistical model code CASTHY [40] for the isotopes investigated in this work. More specifically, the γ -ray strength function for $^{132}$Ba was adjusted to reproduce the available experi- mental capture cross section of Ref. [41]. For JEFF- 3.0A, the HF calculations are not documented, and in JEFF-3.1 an unspecified HF prediction with a Moldauer potential was used for $^{102}$Pd and $^{120}$Te, whereas the CASTHY code was also used for the URR of 130 , $^{132}$Ba. In ENDF/B-VII.0, the URR in $^{102}$Pd was obtained with the GNASH code [42], and for $^{156}$Dy results from EM- PIRE [43] were used. For $^{120}$Te and 130 , $^{132}$Ba the re- spective URR cross sections from JENDL-3.3 have been adopted also in ENDF/B-VII.0. 

## C. Calculation of Maxwellian average cross sections 

In a first step, the evaluated cross sections were folded with the experimental neutron spectrum. The ratios of the measured cross sections and the corresponding aver- 

