Advancement of G T-SCALE and the construction of a graphical user interface
Creators
- 1. California Univ., Berkeley, CA (United States). Dept. of Nuclear Engineering
Description
The issue of advanced reactor concepts with complex core geometries and advanced fuel compositions is being addressed through the development of a new computational methodology based on the coupling of two existing state-of-the-art methodologies - GTRAN2 and SCALE 4.3. The resulting methodology encompasses advanced features in analyzing new designs and in simplifying user-code interactions. The advanced nuclear features include an exact 2 D representation of a complete fuel assembly (or several assemblies), while preserving the heterogeneity of each of its pin cells, flexibility in the energy group structure, a comprehensive cross-section library and material data base, and accurate burnup calculations. A complex graphical user interface along with a graphical presentation of output data make up the user-interaction features of G T-SCALE. Extensive benchmarking of the G T-SCALE is under way, and some results and comparison with other code systems are presented in this paper. (author). 5 refs., 1 fig., 4 tabs
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 11. ENFIR: Meeting on reactor physics and thermal hydraulics
- Imprint Pagination
- 838 p.
- Journal Page Range
- p. 1-6.
Conference
- Title
- Meeting on reactor physics and thermal hydraulics.
- Acronym
- 11. ENFIR
- Dates
- 18-22 Aug 1997.
- Place
- Pocos de Caldas, MG (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 28075467
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- FUEL ELEMENTS; FUELS; G CODES; HETEROGENEOUS REACTOR CORES; MIXED OXIDE FUELS; NUCLEAR ENGINEERING; NUCLEAR FUELS; REACTOR COMPONENTS; REACTOR CORES; REACTOR MATERIALS; REACTOR PHYSICS; REACTOR TECHNOLOGY; REACTORS; S CODES
- Descriptors DEC
- COMPUTER CODES; ENERGY SOURCES; ENGINEERING; MATERIALS; SOLID FUELS
Optional Information
- Notes
- Imprint:Joint nuclear conference with the 4. ENAN: Brazilian meeting on nuclear applications.