Plant inherent control testing in EBR-II
Conference
·
OSTI ID:6570671
A testing program is being conducted in EBR-II to demonstrate passive, inherent reactor protection and control. Data obtained from tests have indicated that the reactor power can be controlled over a large range by the primary coolant flow, secondary coolant flow, and the turbine/generator load. Reactor safety could then be based on inherent safe characteristics of the plant rather than the complicated reactor shutdown system. A Plant Inherent Control Testing (PICT) program is being developed in EBR-II to investigate inherent control concepts for LMR's. The reactor power will be controlled between 40 and 100% power with the primary coolant pumps, the secondary coolant pumps, and the turbine admission valve. The thermal-hydraulic-neutronic system analysis code NATDEMO was used for the pretest predictions of the EBR-II plant response. This paper presents the results of this analysis.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6570671
- Report Number(s):
- CONF-870418-3; ON: DE87007000
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CALCULATIONS
CONTROL ELEMENTS
CONTROL SYSTEMS
EBR-2 REACTOR
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
KINETICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
OPERATION
POWER REACTORS
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR KINETICS
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CALCULATIONS
CONTROL ELEMENTS
CONTROL SYSTEMS
EBR-2 REACTOR
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
KINETICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
OPERATION
POWER REACTORS
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR KINETICS
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS