A three-dimensional PDQ benchmarking comparison with the Advanced Test Reactor measurement data

Conference · Tue Jan 01 04:00:00 EST 1991

OSTI ID:6009903

Kim, S. S.; Judd, J. L.

Flux wire measurements recorded during operation of the Advanced Test Reactor (ATR) were used to validate a three-dimensional (3D) PDQ model developed for the ATR physics analysis in the updated Final Safety Analysis Report (FSAR). The 3D PDQ benchmark analysis utilized the flux synthesis method as well as the explicit method in solving for the spatial flux distribution in the core. Measured data used for comparison were X-Y specific powers in flux wire monitors positioned at the core midplane of the forty fuel elements. Also used were measured data of axial specific power distributions in selected regions of the core for comparison to PDQ generated results. Additionally, ATR lobe ad fuel element powers derived from previously established weighting schemes were available for comparison with PDQ results. Good agreement was achieved in the X-Y-Z specific power comparison of the flux wire data in the fuel elements. However, the PDQ predictions were higher than the measured data in the flux traps because the PDQ model did not have the stainless steel (SS) tubes around the flux wire monitors. The SS tubes were used to position the flux wires. These tubes did not affect the axial profile which was well characterized by the PDQ model. Comparison of the results provided valuable data for the assessment of the 3D analytical model and techniques to be employed in the updated ATR FSAR physics analysis. The study also indicated that the PDQ 3D synthesis solution method is a surprisingly accurate and economical technique for determining global and/or local 3D flux/power distributions in the core. 4 refs., 8 figs., 1 tab.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (USA)
• Sponsoring Organization: DOE; USDOE, Washington, DC (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6009903
• Report Number(s): EGG-M-90347; CONF-910414--30; ON: DE91010096
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ALLOYS
ATR REACTOR
BENCHMARKS
COMPARATIVE EVALUATIONS
COMPUTER CODES
CONTROL ELEMENTS
CROSS SECTIONS
ENRICHED URANIUM REACTORS
FISSION
FLUXMETERS
FUEL ELEMENTS
HIGH ALLOY STEELS
IDAHO NATIONAL ENGINEERING LABORATORY
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION REACTORS
KINETICS
MATERIALS TESTING REACTORS
MEASURING INSTRUMENTS
NATIONAL ORGANIZATIONS
NEUTRON FLUX
NUCLEAR REACTIONS
OPERATION
P CODES
PHYSICS
POWER DENSITY
RADIATION FLUX
REACTIVITY
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTOR MONITORING SYSTEMS
REACTOR OPERATION
REACTOR PHYSICS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
STAINLESS STEELS
STEELS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
THREE-DIMENSIONAL CALCULATIONS
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS