Predicted and measured response of the EBR-II plant to large steam pressure changes

Conference · Thu Jan 01 04:00:00 EST 1987

OSTI ID:6782044

Feldman, E E; Mohr, D; Messick, N C; Chang, L K; Betten, P R; Planchon, H P

The Experimental Breeder Reactor II (EBR-II) is a liquid metal reactor (LMR) whose sodium-bonded metallic fuel core has substantial negative reactivity feedback. It has been demonstrated that this feedback enables a loss-of-flow without scram (LOFWS) to shut the reactor down without operator action. This inherent effect also causes a reactor shutdown following a loss-of-heat-sink without scram (LOHSWS). On April 3, 1986, an LOFWS and an LOHSWS were each performed from full power. In the latter test the secondary sodium flow was reduced to less than 1% about three minutes. This caused the reactor inlet temperature to increase only about 45/sup 0/C and essentially stopped the fission process and shut the reactor down. These tests demonstrated that an LMR plant can be designed in which natural phenomena, rather than electromechanical systems (such as those which move control rods), are effective in protecting the reactor against the potentially adverse consequences of loss-of-primary-flow and loss-of-heat-sink accidents. Moreover, the same phenomena which shut the reactor down during these two tests could be exploited to allow primary flow or inlet temperature, rather than control rods, to be used to maneuver plant output within a considerable power range. This capability would enable an LMR to be designed in which far less reactivity is invested in the control rods than is currently the practice. The ultimate goal is to design an ''inherently safe'' LMR in which reactor safety does not depend upon control rods and also where severe rod withdrawal accidents do not need to be considered.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6782044
• Report Number(s): CONF-870418-1; ON: DE87001580
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
EBR-2 REACTOR
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
OPERATION
POWER REACTORS
PRESSURE GRADIENTS
REACTOR ACCIDENTS
REACTOR OPERATION
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SODIUM COOLED REACTORS