# Bayesian Evaluation Including Covariance Matrices of Neutron-induced Reaction Cross Sections of {sup 181}Ta

## Abstract

A new evaluation of neutron-induced reactions on {sup 181}Ta using a consistent procedure based on Bayesian statistics is presented. Starting point of the evaluation is the description of nuclear reactions via nuclear models implemented in TALYS 1.4. A retrieval of experimental data was performed and covariance matrices of the experiments were generated from an extensive study of the corresponding literature. All reaction channels required for a transport file up to 200 MeV have been considered and the covariance matrices of cross section uncertainties for the most important channels are determined. The evaluation has been performed in one step including all available experimental data. A comparison of the evaluated cross sections and spectra with experimental data and available evaluations is performed. In general the evaluated cross section reflect our best knowledge and give a fair description of the observables. However, there are few deviations from expectation which clearly indicate the impact of the prior and the need to account for model defects. Using the results of the evaluation a complete ENDF-file similarly to those of the TENDL library is generated.

- Authors:

- Publication Date:

- OSTI Identifier:
- 22436775

- Resource Type:
- Journal Article

- Resource Relation:
- Journal Name: Nuclear Data Sheets; Journal Volume: 123; Conference: International workshop on nuclear data covariances, Santa Fe, NM (United States), 28 Apr - 1 May 2014; Other Information: Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)

- Country of Publication:
- United States

- Language:
- English

- Subject:
- 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; COMPARATIVE EVALUATIONS; CROSS SECTIONS; MEV RANGE; NEUTRON REACTIONS; NEUTRONS; NUCLEAR DATA COLLECTIONS; NUCLEAR MODELS; NUCLEAR REACTIONS; STATISTICS; TANTALUM 181

### Citation Formats

```
Leeb, H., E-mail: leeb@kph.tuwien.ac.at, Schnabel, G., Srdinko, Th., and Wildpaner, V.
```*Bayesian Evaluation Including Covariance Matrices of Neutron-induced Reaction Cross Sections of {sup 181}Ta*. United States: N. p., 2015.
Web. doi:10.1016/J.NDS.2014.12.027.

```
Leeb, H., E-mail: leeb@kph.tuwien.ac.at, Schnabel, G., Srdinko, Th., & Wildpaner, V.
```*Bayesian Evaluation Including Covariance Matrices of Neutron-induced Reaction Cross Sections of {sup 181}Ta*. United States. doi:10.1016/J.NDS.2014.12.027.

```
Leeb, H., E-mail: leeb@kph.tuwien.ac.at, Schnabel, G., Srdinko, Th., and Wildpaner, V. Thu .
"Bayesian Evaluation Including Covariance Matrices of Neutron-induced Reaction Cross Sections of {sup 181}Ta". United States.
doi:10.1016/J.NDS.2014.12.027.
```

```
@article{osti_22436775,
```

title = {Bayesian Evaluation Including Covariance Matrices of Neutron-induced Reaction Cross Sections of {sup 181}Ta},

author = {Leeb, H., E-mail: leeb@kph.tuwien.ac.at and Schnabel, G. and Srdinko, Th. and Wildpaner, V.},

abstractNote = {A new evaluation of neutron-induced reactions on {sup 181}Ta using a consistent procedure based on Bayesian statistics is presented. Starting point of the evaluation is the description of nuclear reactions via nuclear models implemented in TALYS 1.4. A retrieval of experimental data was performed and covariance matrices of the experiments were generated from an extensive study of the corresponding literature. All reaction channels required for a transport file up to 200 MeV have been considered and the covariance matrices of cross section uncertainties for the most important channels are determined. The evaluation has been performed in one step including all available experimental data. A comparison of the evaluated cross sections and spectra with experimental data and available evaluations is performed. In general the evaluated cross section reflect our best knowledge and give a fair description of the observables. However, there are few deviations from expectation which clearly indicate the impact of the prior and the need to account for model defects. Using the results of the evaluation a complete ENDF-file similarly to those of the TENDL library is generated.},

doi = {10.1016/J.NDS.2014.12.027},

journal = {Nuclear Data Sheets},

number = ,

volume = 123,

place = {United States},

year = {Thu Jan 15 00:00:00 EST 2015},

month = {Thu Jan 15 00:00:00 EST 2015}

}