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Title: Overview of the use of ATHENA for thermal-hydraulic analysis of systems with lead-bismuth coolant

Abstract

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.

Authors:
;
Publication Date:
Research Org.:
Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
758081
Report Number(s):
INEEL/CON-2000-00127
TRN: US0003758
DOE Contract Number:  
AC07-99ID13727
Resource Type:
Conference
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
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 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

Citation Formats

C. B. Davis, and A. S. Shieh. Overview of the use of ATHENA for thermal-hydraulic analysis of systems with lead-bismuth coolant. United States: N. p., 2000. Web.
C. B. Davis, & A. S. Shieh. Overview of the use of ATHENA for thermal-hydraulic analysis of systems with lead-bismuth coolant. United States.
C. B. Davis, and A. S. Shieh. Sun . "Overview of the use of ATHENA for thermal-hydraulic analysis of systems with lead-bismuth coolant". United States. doi:. https://www.osti.gov/servlets/purl/758081.
@article{osti_758081,
title = {Overview of the use of ATHENA for thermal-hydraulic analysis of systems with lead-bismuth coolant},
author = {C. B. Davis and A. S. Shieh},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Apr 02 00:00:00 EST 2000},
month = {Sun Apr 02 00:00:00 EST 2000}
}

Conference:
Other availability
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