Calculation of Critical Experiment Parameters for the High Flux Isotope Reactor

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

OSTI ID:10108420

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: 10108420
• 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; Other Information: PBD: [1991]
• 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
REACTOR PHYSICS
EXPERIMENT PLANNING
REACTOR OPERATION
CONTROL ELEMENTS
POWER DISTRIBUTION
CROSS SECTIONS
COMPUTER CALCULATIONS
A CODES
B CODES
NUCLEAR DATA COLLECTIONS
FUEL ELEMENTS
X CODES
N CODES
BORON
REACTOR COOLING SYSTEMS
POWER DENSITY
Nuclear Criticality Safety Program (NCSP)
High Flux Isotope Reactor (HFIR)
Critical Configurations
Soluble Boron
Light Water Coolant
K-Effective
Foil Activation Data
220600
220100
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
THEORY AND CALCULATION