Calculation of Critical Experiment Parameters for the High Flux Isotope Reactor

Conference · Sun Mar 08 00:00:00 EST 1992

OSTI ID:6030910

Primm, III, R. T. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Six critical experiments were performed shortly before the initial ascension to power of the High Flux Isotope Reactor (HFIR). Critical configurations were determined at various control rod positions by varying the soluble boron content in the light water coolant. Calculated k-effective was 2% high at beginning-of-life (BOL) typical conditions but was 1.0 at end-of-life (EOL) typical conditions. Axially averaged power distributions for a given radial location were frequently within experimental error. At specific r,z locations with the core, the calculated power densities were significantly different from the experimentally derived values. A reassessment of the foil activation data seems desirable.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6030910
• Report Number(s): CONF-920308-7; ON: DE92004232
• Resource Relation: Conference: American Nuclear Society (ANS) Topical Meeting on Advances in Reactor Physics, Charleston, SC (United States), 8-11 Mar 1992
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
HFIR REACTOR
EXPERIMENT PLANNING
REACTOR PHYSICS
A CODES
B CODES
BORON
COMPUTER CALCULATIONS
CONTROL ELEMENTS
CROSS SECTIONS
FUEL ELEMENTS
N CODES
NUCLEAR DATA COLLECTIONS
POWER DENSITY
POWER DISTRIBUTION
REACTOR COOLING SYSTEMS
REACTOR OPERATION
X CODES
COMPUTER CODES
COOLING SYSTEMS
ELEMENTS
ENRICHED URANIUM REACTORS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
OPERATION
PHYSICS
PLANNING
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SEMIMETALS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
Nuclear Criticality Safety Program (NCSP)
High Flux Isotope Reactor (HFIR)
Critical Configurations
Soluble Boron
Light Water Coolant
K-Effective
Foil Activation Data
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
220100 - Nuclear Reactor Technology- Theory & Calculation