Fast-neutron hodoscope at TREAT: methods for quantiative determination of fuel dispersal
Journal Article
·
· Nucl. Technol.; (United States)
For fuel-motion surveillance in Transient Reactor Test Facility experiments, the fast-neutron hodoscope has advanced beyond its initial ability to provide time, location, and velocity data: its quantitative mass results are now routinely used in liquidmetal fast breeder reactor accident projections. (Mass normalization is based on initial fuel inventory.) The material and radiation surroundings of the test section affect hodoscope detectors in intrinsic and instrumental ways that necessitate detailed corrections. Depending on the experiment, count rate compensation with as little as 5% total imprecision is usually desired for dead time, power-level changes, nonlinear response, efficiency, and background. In addition, systematic effects ranging up to 20% may occur, from such causes as self-shielding, self-multiplication, self-attenuation, and flux depression. For one- to seven-pin bundles, the hodoscope has achieved 1-ms time resolution, 0.25-mm lateral- and 5-mm axial-motion displacement detection, and 50mg single-pin, 350-mg seven-pin mass resolution-not all, however, simultaneously, since resolution and statistical precision are inversely related. The experimental and theoretical foundation for that performance is now well established.
- Research Organization:
- Argonne National Laboratory Reactor Analysis and Safety Division, Argonne, Illinois 60439
- OSTI ID:
- 6922348
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 56; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
AIR COOLED REACTORS
BACKGROUND NOISE
BARYONS
CORRECTIONS
COUNTING RATES
DEAD TIME
DETECTION
EFFICIENCY
ELEMENTARY PARTICLES
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
FAST NEUTRONS
FERMIONS
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENTS
FUEL MOTION DETECTION
FUEL PINS
FUNCTIONS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HADRONS
HODOSCOPES
HOMOGENEOUS REACTORS
MASS RESOLUTION
MULTIPLICATION FACTORS
NEUTRONS
NOISE
NUCLEONS
PERFORMANCE
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESOLUTION
RESPONSE FUNCTIONS
SELF-SHIELDING
SHIELDING
SOLID HOMOGENEOUS REACTORS
SPATIAL RESOLUTION
TEST REACTORS
THERMAL REACTORS
TIME RESOLUTION
TIMING PROPERTIES
TREAT REACTOR
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
AIR COOLED REACTORS
BACKGROUND NOISE
BARYONS
CORRECTIONS
COUNTING RATES
DEAD TIME
DETECTION
EFFICIENCY
ELEMENTARY PARTICLES
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
FAST NEUTRONS
FERMIONS
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENTS
FUEL MOTION DETECTION
FUEL PINS
FUNCTIONS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HADRONS
HODOSCOPES
HOMOGENEOUS REACTORS
MASS RESOLUTION
MULTIPLICATION FACTORS
NEUTRONS
NOISE
NUCLEONS
PERFORMANCE
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESOLUTION
RESPONSE FUNCTIONS
SELF-SHIELDING
SHIELDING
SOLID HOMOGENEOUS REACTORS
SPATIAL RESOLUTION
TEST REACTORS
THERMAL REACTORS
TIME RESOLUTION
TIMING PROPERTIES
TREAT REACTOR