Generation of the WIMS code library from the ENDF/B-VI basic library
Description
The WIMS code is being presently used in many research centers and educational institutions in the world. It has proven to be versatile, reliable and diverse as it is used to calculate different reactor systems. Its data library is rich of useful information that can even be condensed to serve other codes, but the copy distributed with the code is not updated. Some of its data has never been changed, others had changed many times to accommodate certain experimental setups and some data is, simply, not included. This work is an attempt to dominate the techniques used in generating a multigroup library as being applied to the WIMS data library. This new library is called UFMGLIB. A new set of consistent data was generated from the basic ENDF/B-VI library, including complete data for the fission product nuclides and more elaborated burnup chains. The performance of the library is comparable to that of the Standard library accompanying the code and a later library, WIMKAL 88, generated by a group of the Korean Research Institute of Atomic Energy. (author). 38 refs., 40 figs., 30 tabs
Availability note (English)
Available from the Nuclear Information Center of Brazilian Nuclear Energy Commission, Rio de Janeiro.Additional details
Additional titles
- Original title (Portuguese)
- Geracao da biblioteca do codigo WIMS a partir da biblioteca basica ENDF/B-VI
Publishing Information
- Imprint Pagination
- 149 p.
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 27048881
- Subject category
- S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Thesis, Non-conventional Literature
- Descriptors DEI
- BURNUP; E CODES; GROUP CONSTANTS; LIBRARIES; MULTIGROUP THEORY; NEUTRON TRANSPORT THEORY; NUCLEAR DATA COLLECTIONS; NUCLEAR FUELS; NUCLEAR PHYSICS; W CODES
- Descriptors DEC
- COMPUTER CODES; CROSS SECTIONS; ENERGY SOURCES; FUELS; MATERIALS; PHYSICS; REACTOR MATERIALS; TRANSPORT THEORY