Thermal-Hydraulic Analyses of Transients in an Actinide-Burner Reactor Cooled by Forced Convection of Lead Bismuth

Journal Article · Mon Sep 01 00:00:00 EDT 2003 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/S0029-5493(03)00104-3· OSTI ID:911984

Davis, Cliff Bybee

The Idaho National Engineering and Environmental Laboratory (INEEL) and the Massachusetts Institute of Technology (MIT) are investigating the suitability of lead or lead–bismuth cooled fast reactors for producing low-cost electricity as well as for actinide burning. The current analysis evaluated a pool type design that relies on forced circulation of the primary coolant, a conventional steam power conversion system, and a passive decay heat removal system. The ATHENA computer code was used to simulate various transients without reactor scram, including a primary coolant pump trip, a station blackout, and a step reactivity insertion. The reactor design successfully met identified temperature limits for each of the transients analyzed.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: DE-AC07-99ID-13727
• OSTI ID: 911984
• Report Number(s): INEEL/JOU-02-01323; NEDEAU; TRN: US0800255
• Journal Information: Nuclear Engineering and Design, Vol. 224, Issue 2; ISSN 0029-5493
• Country of Publication: United States
• Language: English

Related Subjects

99 - GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
ACTINIDE BURNER REACTORS
ACTINIDES
AFTER-HEAT REMOVAL
BISMUTH
COMPUTER CODES
COOLANTS
DESIGN
ELECTRICITY
FAST REACTORS
FORCED CONVECTION
INEEL
REACTIVITY INSERTIONS
SCRAM
STEAM
TRANSIENTS
actinide-burner
lead-bismuth
reactor
thermal-hydraulic
transients