Published 2004 | Version v1
Miscellaneous

ATHENA-3D for generation IV reactor analysis

  • 1. Idaho National Engineering and Environmental Laboratory, Idaho Falls, Idaho (United States)

Description

ATHENA-3D has been adapted from the RELAP5-3D code for Generation IV reactor analysis. New coolants and components have been implemented or improved, and constitutive models added for heat transfer and pressure drop. Combined with the existing modeling capabilities inherent in the code, it has been shown capable of modeling the design features of some of the Generation IV concepts. To gain confidence in code predictions, however, will require validation using relevant experimental data

Part of:
BE-2004: International meeting on updates in best estimate methods in nuclear installation safety analysis. Proceedings

Additional details

Publishing Information

Imprint Title
BE-2004: International meeting on updates in best estimate methods in nuclear installation safety analysis. Proceedings
Imprint Pagination
376 p.
Journal Page Range
p. 171-176

Conference

Title
International meeting on updates in best estimate methods in nuclear installation safety analysis
Acronym
BE-2004
Dates
14-18 Nov 2004
Place
Washington, DC (United States)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
36058530
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
A CODES; HEAT TRANSFER; LMFBR TYPE REACTORS; MOLTEN SALT REACTORS; R CODES; SAFETY ANALYSIS; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; VALIDATION
Descriptors DEC
BREEDER REACTORS; COMPUTER CODES; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID MECHANICS; HYDRAULICS; LIQUID METAL COOLED REACTORS; MECHANICS; REACTORS; TESTING

Optional Information

Notes
14 refs, 7 figs, 1 tab