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+/openmc_data_downloader-0.6.0.tar.gz
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+%global _empty_manifest_terminate_build 0
+Name:		python-openmc-data-downloader
+Version:	0.6.0
+Release:	1
+Summary:	A tool for selectively downloading h5 files for specified isotopes / elements from your libraries of choice
+License:	MIT License  Copyright (c) 2021 openmc-data-storage  Permission is hereby granted, free of charge, to any person obtaining a copy of this software and associated documentation files (the "Software"), to deal in the Software without restriction, including without limitation the rights to use, copy, modify, merge, publish, distribute, sublicense, and/or sell copies of the Software, and to permit persons to whom the Software is furnished to do so, subject to the following conditions:  The above copyright notice and this permission notice shall be included in all copies or substantial portions of the Software.  THE SOFTWARE IS PROVIDED "AS IS", WITHOUT WARRANTY OF ANY KIND, EXPRESS OR IMPLIED, INCLUDING BUT NOT LIMITED TO THE WARRANTIES OF MERCHANTABILITY, FITNESS FOR A PARTICULAR PURPOSE AND NONINFRINGEMENT. IN NO EVENT SHALL THE AUTHORS OR COPYRIGHT HOLDERS BE LIABLE FOR ANY CLAIM, DAMAGES OR OTHER LIABILITY, WHETHER IN AN ACTION OF CONTRACT, TORT OR OTHERWISE, ARISING FROM, OUT OF OR IN CONNECTION WITH THE SOFTWARE OR THE USE OR OTHER DEALINGS IN THE SOFTWARE. 
+URL:		https://github.com/fusion-energy/openmc_data_downloader
+Source0:	https://mirrors.nju.edu.cn/pypi/web/packages/87/1e/d52fe79c44b0de0b476dd26ae5711301bad1ecd555cde11ffd5d48ad3da2/openmc_data_downloader-0.6.0.tar.gz
+BuildArch:	noarch
+
+Requires:	python3-pandas
+Requires:	python3-retry
+Requires:	python3-pytest
+
+%description
+
+[![CI - Main](https://github.com/openmc-data-storage/openmc_data_downloader/actions/workflows/docker_ci_main.yml/badge.svg)](https://github.com/openmc-data-storage/openmc_data_downloader/actions/workflows/docker_ci_main.yml)
+[![Upload Python Package](https://github.com/openmc-data-storage/openmc_data_downloader/actions/workflows/python-publish.yml/badge.svg)](https://github.com/openmc-data-storage/openmc_data_downloader/actions/workflows/python-publish.yml)
+[![PyPI](https://img.shields.io/pypi/v/openmc_data_downloader?color=brightgreen&label=pypi&logo=grebrightgreenen&logoColor=green)](https://pypi.org/project/openmc_data_downloader/)
+[![codecov](https://codecov.io/gh/openmc-data-storage/openmc_data_downloader/branch/main/graph/badge.svg)](https://codecov.io/gh/openmc-data-storage/openmc_data_downloader)
+
+# OpenMC data downloader
+
+A Python package for downloading preprocessed cross section data in the h5 file
+format for use with OpenMC.
+
+This package allows you to download a fully reproducible composite nuclear data
+library with one command.
+
+There are several methods of obtaining complete data libraries for use with
+OpenMC, for example:
+
+- [OpenMC.org](https://openmc.org/) has entire libraries downloadable as compressed files
+- [OpenMC data repository scripts](https://github.com/openmc-dev/data/) has scripts for automatically downloading ACE and ENDF files and generating h5 files from these inputs.
+
+## History
+
+The package was originally conceived by Jonathan Shimwell as a means of
+downloading a minimal selection of data for use on continuous integration
+platforms.
+The package can also used to produce traceable and reproducible
+nuclear data distributions.
+
+## System Installation
+
+To install the openmc_data_downloader you need to have Python3 installed,
+OpenMC is also advisable if you want to run simulations using the h5 data files
+but not actually mandatory if you just want to download the cross sections.
+
+```bash
+pip install openmc_data_downloader
+```
+
+## Features
+
+The OpenMC data downloader is able to download cross section files for isotopes
+from nuclear data libraries.The user specifies the nuclear data libraries in
+order of their preference. When an isotope is found in multiple libraries it
+will be downloaded from the highest preference library. This avoid duplication
+of isotopes and provides a reproducible nuclear data environment.
+
+The nuclear data h5 file are downloaded from the OpenMC-data-storage
+repository. Prior to being added to the repository they have been automatically
+processed using scripts from OpenMC data repository, these scripts convert ACE
+and ENDF file to h5 files.
+
+The resulting h5 files are then used in and automated test suite of simulations
+to help ensure they are suitable for their intended purpose.
+
+Isotopes for downloading can be found in a variety of ways as demonstrated below.
+When downloading a cross_section.xml file is automatically created and h5 files
+are named with their nuclear data library and the isotope. This helps avoid
+downloading files that already exist locally and the ```overwrite``` argument
+can be used to control if these files are downloaded again.
+
+## Usage - command line usage
+
+### Getting a description of the input options
+
+```bash
+openmc_data_downloader --help
+```
+
+### Downloading a single isotope from the FENDL 3.1d nuclear library
+
+```bash
+openmc_data_downloader -l FENDL-3.1d -i Li6
+```
+
+### Downloading a multiple isotopes from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -i Li6 Li7
+```
+
+### Downloading a single element from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -e Li
+```
+
+### Downloading a multiple element from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -e Li Si Na
+```
+
+### Downloading h5 files from the ENDF/B 7.1 NNDC library to a specific folder (destination)
+
+```bash
+openmc_data_downloader -l ENDFB-7.1-NNDC -i Be9 -d my_h5_files
+```
+
+### Downloading a combination of isotopes and element from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -e Li Si Na -i Fe56 U235
+```
+### Downloading all the isotopes from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -i all
+```
+### Downloading all the stable isotopes from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -i stable
+```
+
+### Downloading all the isotopes in a materials.xml file from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -m materials.xml
+```
+
+### Downloading 3 isotopes from ENDF/B 7.1 NNDC (first choice) and TENDL 2019 (second choice) nuclear library
+
+```bash
+openmc_data_downloader -l ENDFB-7.1-NNDC TENDL-2019 -i Li6 Li7 Be9
+```
+
+### Downloading the photon only cross section for an element ENDF/B 7.1 NNDC
+
+```bash
+openmc_data_downloader -l ENDFB-7.1-NNDC -e Li -p photon 
+```
+
+### Downloading the neutron and photon cross section for an element ENDF/B 7.1 NNDC
+
+```bash
+openmc_data_downloader -l ENDFB-7.1-NNDC -e Li -p neutron photon
+```
+
+### Downloading the neutron cross section for elements and an SaB cross sections
+
+```bash
+openmc_data_downloader -l ENDFB-7.1-NNDC -e Be O -s c_Be_in_BeO
+```
+
+## Usage - within a Python environment
+
+When using the Python API the ```just_in_time_library_generator()``` function
+provides similar capabilities to the ```openmc_data_downloader``` terminal
+command. With one key difference being that ```just_in_time_library_generator()```
+sets the ```OPENMC_CROSS_SECTIONS``` environmental variable to point to the
+newly created cross_sections.xml by default.
+
+### Downloading the isotopes present in an OpenMC material
+
+```python
+import openmc
+import openmc_data_downloader as odd
+
+mat1 = openmc.Material()
+mat1.add_element('Fe', 0.95)
+mat1.add_element('C', 0.05)
+
+odd.just_in_time_library_generator(
+    libraries='FENDL-3.1d',
+    materials=mat1
+)
+```
+
+### Downloading the isotopes present in an OpenMC material from two libraries but with a preference for ENDF/B 7.1 NNDC library over TENDL 2019
+
+```python
+import openmc
+import openmc_data_downloader as odd
+
+mat1 = openmc.Material()
+mat1.add_element('Fe', 0.95)
+mat1.add_element('C', 0.05)
+
+odd.just_in_time_library_generator(
+    libraries=['ENDFB-7.1-NNDC', 'TENDL-2019'],
+    materials=mat1
+)
+```
+
+### Downloading the isotopes in several OpenMC materials
+
+```python
+import openmc
+import openmc_data_downloader as odd
+
+mat1 = openmc.Material()
+mat1.add_element('Fe', 0.95)
+mat1.add_element('C', 0.05)
+
+mat2 = openmc.Material()
+mat2.add_element('H', 0.66)
+mat2.add_element('0', 0.33)
+
+# a list of openmc.Material objects can be used
+odd.just_in_time_library_generator(
+    libraries='ENDFB-7.1-NNDC',
+    materials=[mat1, mat2]
+)
+
+# alternatively an openmc.Materials() object can be used
+mats = openmc.Materials([mat1, mat2]) 
+odd.just_in_time_library_generator(
+    libraries='ENDFB-7.1-NNDC',
+    materials=mats
+)
+```
+
+### Downloading neutron cross sections for a material with an SaB
+
+```python
+import openmc
+import openmc_data_downloader as odd
+
+my_mat = openmc.Material()
+my_mat.add_element('Be', 0.5)
+my_mat.add_element('O', 0.5)
+my_mat.add_s_alpha_beta('Be_in_BeO')
+
+odd.just_in_time_library_generator(
+    libraries='ENDFB-7.1-NNDC',
+    materials= my_mat
+    particles = ['neutron'],
+)
+```
+
+### Downloading photon and neutron cross sections for isotopes and elements from the TENDL 2019 library
+
+```python
+import openmc
+import openmc_data_downloader as odd
+
+odd.just_in_time_library_generator(
+    libraries='TENDL-2019',
+    elements=['Li', 'Be'],
+    particles = ['photon', 'neutron'],
+    isotopes=['Fe56', 'U235'],
+)
+```
+
+
+%package -n python3-openmc-data-downloader
+Summary:	A tool for selectively downloading h5 files for specified isotopes / elements from your libraries of choice
+Provides:	python-openmc-data-downloader
+BuildRequires:	python3-devel
+BuildRequires:	python3-setuptools
+BuildRequires:	python3-pip
+%description -n python3-openmc-data-downloader
+
+[![CI - Main](https://github.com/openmc-data-storage/openmc_data_downloader/actions/workflows/docker_ci_main.yml/badge.svg)](https://github.com/openmc-data-storage/openmc_data_downloader/actions/workflows/docker_ci_main.yml)
+[![Upload Python Package](https://github.com/openmc-data-storage/openmc_data_downloader/actions/workflows/python-publish.yml/badge.svg)](https://github.com/openmc-data-storage/openmc_data_downloader/actions/workflows/python-publish.yml)
+[![PyPI](https://img.shields.io/pypi/v/openmc_data_downloader?color=brightgreen&label=pypi&logo=grebrightgreenen&logoColor=green)](https://pypi.org/project/openmc_data_downloader/)
+[![codecov](https://codecov.io/gh/openmc-data-storage/openmc_data_downloader/branch/main/graph/badge.svg)](https://codecov.io/gh/openmc-data-storage/openmc_data_downloader)
+
+# OpenMC data downloader
+
+A Python package for downloading preprocessed cross section data in the h5 file
+format for use with OpenMC.
+
+This package allows you to download a fully reproducible composite nuclear data
+library with one command.
+
+There are several methods of obtaining complete data libraries for use with
+OpenMC, for example:
+
+- [OpenMC.org](https://openmc.org/) has entire libraries downloadable as compressed files
+- [OpenMC data repository scripts](https://github.com/openmc-dev/data/) has scripts for automatically downloading ACE and ENDF files and generating h5 files from these inputs.
+
+## History
+
+The package was originally conceived by Jonathan Shimwell as a means of
+downloading a minimal selection of data for use on continuous integration
+platforms.
+The package can also used to produce traceable and reproducible
+nuclear data distributions.
+
+## System Installation
+
+To install the openmc_data_downloader you need to have Python3 installed,
+OpenMC is also advisable if you want to run simulations using the h5 data files
+but not actually mandatory if you just want to download the cross sections.
+
+```bash
+pip install openmc_data_downloader
+```
+
+## Features
+
+The OpenMC data downloader is able to download cross section files for isotopes
+from nuclear data libraries.The user specifies the nuclear data libraries in
+order of their preference. When an isotope is found in multiple libraries it
+will be downloaded from the highest preference library. This avoid duplication
+of isotopes and provides a reproducible nuclear data environment.
+
+The nuclear data h5 file are downloaded from the OpenMC-data-storage
+repository. Prior to being added to the repository they have been automatically
+processed using scripts from OpenMC data repository, these scripts convert ACE
+and ENDF file to h5 files.
+
+The resulting h5 files are then used in and automated test suite of simulations
+to help ensure they are suitable for their intended purpose.
+
+Isotopes for downloading can be found in a variety of ways as demonstrated below.
+When downloading a cross_section.xml file is automatically created and h5 files
+are named with their nuclear data library and the isotope. This helps avoid
+downloading files that already exist locally and the ```overwrite``` argument
+can be used to control if these files are downloaded again.
+
+## Usage - command line usage
+
+### Getting a description of the input options
+
+```bash
+openmc_data_downloader --help
+```
+
+### Downloading a single isotope from the FENDL 3.1d nuclear library
+
+```bash
+openmc_data_downloader -l FENDL-3.1d -i Li6
+```
+
+### Downloading a multiple isotopes from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -i Li6 Li7
+```
+
+### Downloading a single element from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -e Li
+```
+
+### Downloading a multiple element from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -e Li Si Na
+```
+
+### Downloading h5 files from the ENDF/B 7.1 NNDC library to a specific folder (destination)
+
+```bash
+openmc_data_downloader -l ENDFB-7.1-NNDC -i Be9 -d my_h5_files
+```
+
+### Downloading a combination of isotopes and element from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -e Li Si Na -i Fe56 U235
+```
+### Downloading all the isotopes from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -i all
+```
+### Downloading all the stable isotopes from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -i stable
+```
+
+### Downloading all the isotopes in a materials.xml file from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -m materials.xml
+```
+
+### Downloading 3 isotopes from ENDF/B 7.1 NNDC (first choice) and TENDL 2019 (second choice) nuclear library
+
+```bash
+openmc_data_downloader -l ENDFB-7.1-NNDC TENDL-2019 -i Li6 Li7 Be9
+```
+
+### Downloading the photon only cross section for an element ENDF/B 7.1 NNDC
+
+```bash
+openmc_data_downloader -l ENDFB-7.1-NNDC -e Li -p photon 
+```
+
+### Downloading the neutron and photon cross section for an element ENDF/B 7.1 NNDC
+
+```bash
+openmc_data_downloader -l ENDFB-7.1-NNDC -e Li -p neutron photon
+```
+
+### Downloading the neutron cross section for elements and an SaB cross sections
+
+```bash
+openmc_data_downloader -l ENDFB-7.1-NNDC -e Be O -s c_Be_in_BeO
+```
+
+## Usage - within a Python environment
+
+When using the Python API the ```just_in_time_library_generator()``` function
+provides similar capabilities to the ```openmc_data_downloader``` terminal
+command. With one key difference being that ```just_in_time_library_generator()```
+sets the ```OPENMC_CROSS_SECTIONS``` environmental variable to point to the
+newly created cross_sections.xml by default.
+
+### Downloading the isotopes present in an OpenMC material
+
+```python
+import openmc
+import openmc_data_downloader as odd
+
+mat1 = openmc.Material()
+mat1.add_element('Fe', 0.95)
+mat1.add_element('C', 0.05)
+
+odd.just_in_time_library_generator(
+    libraries='FENDL-3.1d',
+    materials=mat1
+)
+```
+
+### Downloading the isotopes present in an OpenMC material from two libraries but with a preference for ENDF/B 7.1 NNDC library over TENDL 2019
+
+```python
+import openmc
+import openmc_data_downloader as odd
+
+mat1 = openmc.Material()
+mat1.add_element('Fe', 0.95)
+mat1.add_element('C', 0.05)
+
+odd.just_in_time_library_generator(
+    libraries=['ENDFB-7.1-NNDC', 'TENDL-2019'],
+    materials=mat1
+)
+```
+
+### Downloading the isotopes in several OpenMC materials
+
+```python
+import openmc
+import openmc_data_downloader as odd
+
+mat1 = openmc.Material()
+mat1.add_element('Fe', 0.95)
+mat1.add_element('C', 0.05)
+
+mat2 = openmc.Material()
+mat2.add_element('H', 0.66)
+mat2.add_element('0', 0.33)
+
+# a list of openmc.Material objects can be used
+odd.just_in_time_library_generator(
+    libraries='ENDFB-7.1-NNDC',
+    materials=[mat1, mat2]
+)
+
+# alternatively an openmc.Materials() object can be used
+mats = openmc.Materials([mat1, mat2]) 
+odd.just_in_time_library_generator(
+    libraries='ENDFB-7.1-NNDC',
+    materials=mats
+)
+```
+
+### Downloading neutron cross sections for a material with an SaB
+
+```python
+import openmc
+import openmc_data_downloader as odd
+
+my_mat = openmc.Material()
+my_mat.add_element('Be', 0.5)
+my_mat.add_element('O', 0.5)
+my_mat.add_s_alpha_beta('Be_in_BeO')
+
+odd.just_in_time_library_generator(
+    libraries='ENDFB-7.1-NNDC',
+    materials= my_mat
+    particles = ['neutron'],
+)
+```
+
+### Downloading photon and neutron cross sections for isotopes and elements from the TENDL 2019 library
+
+```python
+import openmc
+import openmc_data_downloader as odd
+
+odd.just_in_time_library_generator(
+    libraries='TENDL-2019',
+    elements=['Li', 'Be'],
+    particles = ['photon', 'neutron'],
+    isotopes=['Fe56', 'U235'],
+)
+```
+
+
+%package help
+Summary:	Development documents and examples for openmc-data-downloader
+Provides:	python3-openmc-data-downloader-doc
+%description help
+
+[![CI - Main](https://github.com/openmc-data-storage/openmc_data_downloader/actions/workflows/docker_ci_main.yml/badge.svg)](https://github.com/openmc-data-storage/openmc_data_downloader/actions/workflows/docker_ci_main.yml)
+[![Upload Python Package](https://github.com/openmc-data-storage/openmc_data_downloader/actions/workflows/python-publish.yml/badge.svg)](https://github.com/openmc-data-storage/openmc_data_downloader/actions/workflows/python-publish.yml)
+[![PyPI](https://img.shields.io/pypi/v/openmc_data_downloader?color=brightgreen&label=pypi&logo=grebrightgreenen&logoColor=green)](https://pypi.org/project/openmc_data_downloader/)
+[![codecov](https://codecov.io/gh/openmc-data-storage/openmc_data_downloader/branch/main/graph/badge.svg)](https://codecov.io/gh/openmc-data-storage/openmc_data_downloader)
+
+# OpenMC data downloader
+
+A Python package for downloading preprocessed cross section data in the h5 file
+format for use with OpenMC.
+
+This package allows you to download a fully reproducible composite nuclear data
+library with one command.
+
+There are several methods of obtaining complete data libraries for use with
+OpenMC, for example:
+
+- [OpenMC.org](https://openmc.org/) has entire libraries downloadable as compressed files
+- [OpenMC data repository scripts](https://github.com/openmc-dev/data/) has scripts for automatically downloading ACE and ENDF files and generating h5 files from these inputs.
+
+## History
+
+The package was originally conceived by Jonathan Shimwell as a means of
+downloading a minimal selection of data for use on continuous integration
+platforms.
+The package can also used to produce traceable and reproducible
+nuclear data distributions.
+
+## System Installation
+
+To install the openmc_data_downloader you need to have Python3 installed,
+OpenMC is also advisable if you want to run simulations using the h5 data files
+but not actually mandatory if you just want to download the cross sections.
+
+```bash
+pip install openmc_data_downloader
+```
+
+## Features
+
+The OpenMC data downloader is able to download cross section files for isotopes
+from nuclear data libraries.The user specifies the nuclear data libraries in
+order of their preference. When an isotope is found in multiple libraries it
+will be downloaded from the highest preference library. This avoid duplication
+of isotopes and provides a reproducible nuclear data environment.
+
+The nuclear data h5 file are downloaded from the OpenMC-data-storage
+repository. Prior to being added to the repository they have been automatically
+processed using scripts from OpenMC data repository, these scripts convert ACE
+and ENDF file to h5 files.
+
+The resulting h5 files are then used in and automated test suite of simulations
+to help ensure they are suitable for their intended purpose.
+
+Isotopes for downloading can be found in a variety of ways as demonstrated below.
+When downloading a cross_section.xml file is automatically created and h5 files
+are named with their nuclear data library and the isotope. This helps avoid
+downloading files that already exist locally and the ```overwrite``` argument
+can be used to control if these files are downloaded again.
+
+## Usage - command line usage
+
+### Getting a description of the input options
+
+```bash
+openmc_data_downloader --help
+```
+
+### Downloading a single isotope from the FENDL 3.1d nuclear library
+
+```bash
+openmc_data_downloader -l FENDL-3.1d -i Li6
+```
+
+### Downloading a multiple isotopes from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -i Li6 Li7
+```
+
+### Downloading a single element from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -e Li
+```
+
+### Downloading a multiple element from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -e Li Si Na
+```
+
+### Downloading h5 files from the ENDF/B 7.1 NNDC library to a specific folder (destination)
+
+```bash
+openmc_data_downloader -l ENDFB-7.1-NNDC -i Be9 -d my_h5_files
+```
+
+### Downloading a combination of isotopes and element from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -e Li Si Na -i Fe56 U235
+```
+### Downloading all the isotopes from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -i all
+```
+### Downloading all the stable isotopes from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -i stable
+```
+
+### Downloading all the isotopes in a materials.xml file from the TENDL 2019 nuclear library
+
+```bash
+openmc_data_downloader -l TENDL-2019 -m materials.xml
+```
+
+### Downloading 3 isotopes from ENDF/B 7.1 NNDC (first choice) and TENDL 2019 (second choice) nuclear library
+
+```bash
+openmc_data_downloader -l ENDFB-7.1-NNDC TENDL-2019 -i Li6 Li7 Be9
+```
+
+### Downloading the photon only cross section for an element ENDF/B 7.1 NNDC
+
+```bash
+openmc_data_downloader -l ENDFB-7.1-NNDC -e Li -p photon 
+```
+
+### Downloading the neutron and photon cross section for an element ENDF/B 7.1 NNDC
+
+```bash
+openmc_data_downloader -l ENDFB-7.1-NNDC -e Li -p neutron photon
+```
+
+### Downloading the neutron cross section for elements and an SaB cross sections
+
+```bash
+openmc_data_downloader -l ENDFB-7.1-NNDC -e Be O -s c_Be_in_BeO
+```
+
+## Usage - within a Python environment
+
+When using the Python API the ```just_in_time_library_generator()``` function
+provides similar capabilities to the ```openmc_data_downloader``` terminal
+command. With one key difference being that ```just_in_time_library_generator()```
+sets the ```OPENMC_CROSS_SECTIONS``` environmental variable to point to the
+newly created cross_sections.xml by default.
+
+### Downloading the isotopes present in an OpenMC material
+
+```python
+import openmc
+import openmc_data_downloader as odd
+
+mat1 = openmc.Material()
+mat1.add_element('Fe', 0.95)
+mat1.add_element('C', 0.05)
+
+odd.just_in_time_library_generator(
+    libraries='FENDL-3.1d',
+    materials=mat1
+)
+```
+
+### Downloading the isotopes present in an OpenMC material from two libraries but with a preference for ENDF/B 7.1 NNDC library over TENDL 2019
+
+```python
+import openmc
+import openmc_data_downloader as odd
+
+mat1 = openmc.Material()
+mat1.add_element('Fe', 0.95)
+mat1.add_element('C', 0.05)
+
+odd.just_in_time_library_generator(
+    libraries=['ENDFB-7.1-NNDC', 'TENDL-2019'],
+    materials=mat1
+)
+```
+
+### Downloading the isotopes in several OpenMC materials
+
+```python
+import openmc
+import openmc_data_downloader as odd
+
+mat1 = openmc.Material()
+mat1.add_element('Fe', 0.95)
+mat1.add_element('C', 0.05)
+
+mat2 = openmc.Material()
+mat2.add_element('H', 0.66)
+mat2.add_element('0', 0.33)
+
+# a list of openmc.Material objects can be used
+odd.just_in_time_library_generator(
+    libraries='ENDFB-7.1-NNDC',
+    materials=[mat1, mat2]
+)
+
+# alternatively an openmc.Materials() object can be used
+mats = openmc.Materials([mat1, mat2]) 
+odd.just_in_time_library_generator(
+    libraries='ENDFB-7.1-NNDC',
+    materials=mats
+)
+```
+
+### Downloading neutron cross sections for a material with an SaB
+
+```python
+import openmc
+import openmc_data_downloader as odd
+
+my_mat = openmc.Material()
+my_mat.add_element('Be', 0.5)
+my_mat.add_element('O', 0.5)
+my_mat.add_s_alpha_beta('Be_in_BeO')
+
+odd.just_in_time_library_generator(
+    libraries='ENDFB-7.1-NNDC',
+    materials= my_mat
+    particles = ['neutron'],
+)
+```
+
+### Downloading photon and neutron cross sections for isotopes and elements from the TENDL 2019 library
+
+```python
+import openmc
+import openmc_data_downloader as odd
+
+odd.just_in_time_library_generator(
+    libraries='TENDL-2019',
+    elements=['Li', 'Be'],
+    particles = ['photon', 'neutron'],
+    isotopes=['Fe56', 'U235'],
+)
+```
+
+
+%prep
+%autosetup -n openmc-data-downloader-0.6.0
+
+%build
+%py3_build
+
+%install
+%py3_install
+install -d -m755 %{buildroot}/%{_pkgdocdir}
+if [ -d doc ]; then cp -arf doc %{buildroot}/%{_pkgdocdir}; fi
+if [ -d docs ]; then cp -arf docs %{buildroot}/%{_pkgdocdir}; fi
+if [ -d example ]; then cp -arf example %{buildroot}/%{_pkgdocdir}; fi
+if [ -d examples ]; then cp -arf examples %{buildroot}/%{_pkgdocdir}; fi
+pushd %{buildroot}
+if [ -d usr/lib ]; then
+	find usr/lib -type f -printf "/%h/%f\n" >> filelist.lst
+fi
+if [ -d usr/lib64 ]; then
+	find usr/lib64 -type f -printf "/%h/%f\n" >> filelist.lst
+fi
+if [ -d usr/bin ]; then
+	find usr/bin -type f -printf "/%h/%f\n" >> filelist.lst
+fi
+if [ -d usr/sbin ]; then
+	find usr/sbin -type f -printf "/%h/%f\n" >> filelist.lst
+fi
+touch doclist.lst
+if [ -d usr/share/man ]; then
+	find usr/share/man -type f -printf "/%h/%f.gz\n" >> doclist.lst
+fi
+popd
+mv %{buildroot}/filelist.lst .
+mv %{buildroot}/doclist.lst .
+
+%files -n python3-openmc-data-downloader -f filelist.lst
+%dir %{python3_sitelib}/*
+
+%files help -f doclist.lst
+%{_docdir}/*
+
+%changelog
+* Thu May 18 2023 Python_Bot <Python_Bot@openeuler.org> - 0.6.0-1
+- Package Spec generated
diff --git a/sources b/sources
new file mode 100644
index 0000000..6a2f546
--- /dev/null
+++ b/sources
@@ -0,0 +1 @@
+0c3e9c4af588120a0e3395edd921ff09  openmc_data_downloader-0.6.0.tar.gz