Overview of the use of ATHENA for thermal-hydraulic analysis of systems with lead-bismuth coolant
The INEEL and MIT are investigating the suitability of lead-bismuth cooled fast reactor for producing low-cost electricity as well as for actinide burning. This paper is concerned with the general area of thermal-hydraulics of lead-bismuth cooled reactors. The ATHENA code is being used in the thermal-hydraulic design and analysis of lead-bismuth cooled reactors. The ATHENA code was reviewed to determine its applicability for simulating lead-bismuth cooled reactors. Two modifications were made to the code as a result of this review. Specifically, a correlation to represent heat transfer from rod bundles to a liquid metal and a void correlation based on data taken in a mixture of lead-bismuth and steam were added the code. The paper also summarizes the analytical work that is being performed with the code and plans for future analytical work.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- AC07-99ID13727
- OSTI ID:
- 758081
- Report Number(s):
- INEEL/CON-2000-00127; TRN: US0003758
- Resource Relation:
- Conference: 8th International Conference on Nuclear Engineering (ICONE-8), Baltimore, MD (US), 04/02/2000--04/06/2000; Other Information: PBD: 2 Apr 2000
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
LIQUID METAL COOLED REACTORS
FAST REACTORS
A CODES
HEAT TRANSFER
HYDRAULICS
ACTINIDE BURNER REACTORS
LEAD-BISMUTH
COOLANT
FAST REACTOR
ATHENA
THERMAL-HYDRAULICS