An evaluation of LMR design options for reduction of sodium void worth

Conference · Sun Jan 01 04:00:00 EST 1989

OSTI ID:7261882

Hill, R N; Khalil, H

In this study, we analyze the relationship between the sodium void worth ({rho}{sub NA}) and other important performance characteristics for various design options which reduce {rho}{sub NA}. Our objective was to identify a preferred design option for reducing {rho}{sub NA} based on an overall consideration of performance tradeoffs. The focus of this study is on core designs of recent interest in the US LMR program, i.e. designs in the 450 to 1200 MWt size range that make use of metal alloy fuel. A key objective of the LMR development program in the US has been to design cores that can passively avoid damage when the control rods fail to scram in response to postulated accident initiators (e.g. inadvertent reactivity insertion or loss of coolant flow). Analyses and experimental tests of such unprotected events have demonstrated that the physical properties of metallic fuel alloys and the neutronic feedback characteristics of metal-fueled cores can be exploited to obtain favorable relations among the power, power/flow, and inlet temperature coefficients of reactivity and, consequently, large margins to sodium boiling and fuel damage under accident conditions. Since the reactivity effects of sodium density variation during postulated accidents are effectively compensated by other feedback effects, reduction of the sodium void worth has not been a primary design objective for recent LMR concepts; relatively large values ($4 to $6) are predicted for current core designs. 23 refs., 11 figs.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 7261882
• Report Number(s): CONF-900418-3; ON: DE90003824
• Country of Publication: United States
• Language: English

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42 ENGINEERING
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99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ALLOYS
BREEDER REACTORS
BREEDING BLANKETS
BREEDING RATIO
BURNUP
COMPARATIVE EVALUATIONS
COMPUTER CODES
CONVERSION RATIO
COOLING SYSTEMS
DAMAGE
DATA PROCESSING
DENSITY
DESIGN
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAILURE MODE ANALYSIS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FEEDBACK
FISSILE MATERIALS
FISSION PRODUCTS
FISSIONABLE MATERIALS
FLUID MECHANICS
FUEL ELEMENTS
GEOMETRY
HEAT TRANSFER
HYDRAULICS
ISOTOPES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MATERIALS TESTING
MATHEMATICS
MEASURING METHODS
MECHANICS
METAL MODERATED REACTORS
MODERATORS
PERFORMANCE TESTING
PHYSICAL PROPERTIES
PLANNING
POWER GENERATION
PROCESSING
R CODES
RADIOACTIVE MATERIALS
REACTIVITY
REACTIVITY COEFFICIENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR SAFETY
REACTORS
RECOMMENDATIONS
RESEARCH PROGRAMS
RUPTURES
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TEMPERATURE COEFFICIENT
TESTING
TRANSIENTS