Plant inherent control testing in EBR-II
Recent tests in the Experimental Breeder Reactor II (EBR-II) have demonstrated that reactor feedbacks can passively reduce power and thus effectively mitigate reactor undercooling caused by equipment failures. A follow-on testing program is being designed to investigate the use of these feedbacks along other liquid metal reactor (LMR) characteristics to routinely control reactor power during plant maneuvers and fuel burnup, compensation, and to limit the possibility and consequences of over-power accidents. In all of the tests described in the present paper, the control rods will not be used as the plant is maneuvered over the power range between 40 and 100%. The plant variables (forcing functions) employed in the power control include the primary flow, the secondary flow, and the turbine admission position. The pretest predictions for the tests are presented and a preliminary analysis on the effects of controller failures is discussed. This paper provides concepts in reactor power control which may lead to fundamental changes in design and safety consideration of metal fueled LMRs.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6236974
- Report Number(s):
- CONF-870418-3-FP; ON: DE87011532
- Resource Relation:
- Conference: Topical meeting on anticipated and abnormal transients in nuclear power plants, Atlanta, GA, USA, 12 Apr 1987; Other Information: Paper copy only, copy does not permit microfiche production
- Country of Publication:
- United States
- Language:
- English
Similar Records
Predicted and measured response of the EBR-II plant to large steam pressure changes
Results and implications of the EBR-II inherent safety demonstration tests
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
EBR-2 REACTOR
CONTROL
REACTOR OPERATION
HEAT TRANSFER
POWER DISTRIBUTION
PRIMARY COOLANT CIRCUITS
REACTOR CONTROL SYSTEMS
BREEDER REACTORS
CONTROL SYSTEMS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
OPERATION
POWER REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
220400* - Nuclear Reactor Technology- Control Systems
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors
210500 - Power Reactors
Breeding