SASSYS analysis of EBR-II SHRT experiments

Conference · Thu Jan 01 00:00:00 EST 1987 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6941599

Hill, D J

The SASSYS-1 systems thermal-hydraulic code for LMRs has been applied to the analysis of selected EBR-II SHRT experiments. The results show that SASSYS can predict the transient thermal-hydraulic and reactivity behavior of EBR-II under these conditions. This contributes to the validation of the modeling of EBR-II with SASSYS and of the code itself. The next step is blind post-test analysis of the unprotected transients performed in EBR-II.

• Research Organization: Argonne National Lab., IL (USA)
• OSTI ID: 6941599
• Report Number(s): CONF-8711195-; TRN: 88-032046
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 55; Conference: American Nuclear Society winter meeting, Los Angeles, CA, USA, 15 Nov 1987
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
EBR-2 REACTOR
HEAT TRANSFER
HYDRAULICS
REACTOR KINETICS
REACTOR SAFETY EXPERIMENTS
RHR SYSTEMS
S CODES
AFTER-HEAT REMOVAL
NATURAL CONVECTION
POWER DISTRIBUTION
PUMPS
REACTIVITY
TRANSIENTS
BREEDER REACTORS
COMPUTER CODES
CONVECTION
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
KINETICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MASS TRANSFER
MECHANICS
POWER REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
REMOVAL
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding