SASSYS validation with the EBR-II (Experimental Breeder Reactor II) shutdown heat removal tests

Conference · Wed Nov 01 00:00:00 EST 1989 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5486959

Herzog, J P ^[1]

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1. Argonne National Laboratory, IL (USA)

SASSYS-1 is a coupled neutronic and thermal-hydraulic code developed for the analysis of transients in liquid-metal-cooled reactors (LMRs). The code is especially suited for evaluating off-normal reactor transients - protected design-basis accidents and unprotected anticipated transients without scram. Because SASSYS is heavily used in support of the Integral Fast Reactor concept and of innovative LMR designs, such as PRISM, a strong validation base for the code must exist. Part of the validation process for SASSYS is analysis of experiments performed on operating reactors, such as the metal-fueled Experimental Breeder Reactor II (EBR-II). During the course of a series of historic whole-plant experiments, EBR-II illustrated key safety features of metal-fueled LMRs. These experiments, the shutdown heat removal tests (SHRTs), culminated in unprotected loss of flow and loss of heat sink transients from full power and flow. Analysis of these and earlier SHRT experiments constitutes a vital part of SASSYS validation, because it facilitates scrutiny of specific SASSYS models and of integrated code capability.

• OSTI ID: 5486959
• Report Number(s): CONF-891103-; CODEN: TANSA; TRN: 91-024691
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 60; Conference: Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit, San Francisco, CA (United States), 26-30 Nov 1989; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LIQUID METAL COOLED REACTORS
REACTOR KINETICS
S CODES
VALIDATION
AFTER-HEAT REMOVAL
ATWS
DESIGN
EBR-2 REACTOR
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
REACTIVITY
REACTOR ACCIDENTS
REACTOR PHYSICS
REACTOR SHUTDOWN
TRANSIENTS
ACCIDENTS
BREEDER REACTORS
COMPUTER CODES
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
KINETICS
LMFBR TYPE REACTORS
MECHANICS
PHYSICS
POWER REACTORS
REACTORS
REMOVAL
RESEARCH AND TEST REACTORS
SHUTDOWN
SODIUM COOLED REACTORS
TESTING
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding