Critical Experiment Tests of Bowing and Expansion Reactivity Calculations for LMRS

Conference · Sun Sep 18 00:00:00 EDT 1988

OSTI ID:6457983

Schaefer, R. W. ^[1]

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1. Argonne National Laboratory, Idaho Falls, IL (United States)

Experiments done in several LMR-type critical assemblies simulated core axial expansion, core radial expansion and bowing, coolant expansion, and control driveline expansion. For the most part new experimental techniques were developed to do these experiments. Calculations of the experiments basically used design-level methods, except when it was necessary to investigate complexities peculiar to the experiments. It was found that these feedback reactivities generally are overpredicted, but the predictions are within 30% of the experimental values.

• Research Organization: Argonne National Laboratory, Idaho Falls, IL (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Nuclear Energy Programs
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6457983
• Report Number(s): CONF-880911-32; ON: DE89005865; TRN: 89-003809
• Resource Relation: Conference: International Reactor Physics Conference , Jackson Hole, WY (United States), 18-21 Sep 1988; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CONTROL ELEMENTS
EXPANSION
CONTROL ROD DRIVES
FUEL ELEMENTS
LMFBR TYPE REACTORS
REACTOR PHYSICS
REACTOR COOLING SYSTEMS
REACTOR CORES
DEFORMATION
EXPERIMENTAL DATA
FEEDBACK
REACTIVITY
RESEARCH PROGRAMS
SODIUM
ZPPR REACTOR
ALKALI METALS
BREEDER REACTORS
COOLING SYSTEMS
DATA
ELEMENTS
ENERGY SYSTEMS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
INFORMATION
LIQUID METAL COOLED REACTORS
METALS
NUMERICAL DATA
PHYSICS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
ZERO POWER REACTORS
Nuclear Criticality Safety Program (NCSP)
Liquid-Metal-Cooled Fast Reactor (LMR)
Zero Power Physics Reactor (ZPPR)
Coolant Expansion
Uniform Expansion
Fuel Shifting
All-Plate Shifting
Bowing Oscillator
Core Nonuniformities
Single-Fuel-Column (SFC)
Double-Fuel-Column (DFC)
210500* - Power Reactors
Breeding