Published 1997 | Version v1
Miscellaneous

Advancement of G T-SCALE and the construction of a graphical user interface

  • 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

Part of:
Proceedings of the 11. ENFIR: Meeting on reactor physics and thermal hydraulics

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.