PDQ physics analysis for the ATR-FSAR upgrade
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:7231349
- EG and G Idaho, Inc., Idaho Falls (United States)
The final safety analysis report (FSAR) for the Advanced Test Reactor (ATR) is presently being updated at the Idaho National Engineering Laboratory and will use the US Nuclear Regulatory Commission's FSAR format as a guide to provide a safety analysis comparable with that used throughout the commercial nuclear industry. In upgrading the FSAR, an updated reactor core physics analysis is performed on the unique serpentine core design. Unlike the two-dimensional (2D) partial core model used in the original FSAR, this new physics analysis uses both 2D and Three-dimensional (3D) PDQ full-core models employing the most recent cross-section data libraries. The 2D PDQ benchmark comparison provides a reliable validation for the ATR FSAR power distribution calculations. And the new full-core depletion analysis now provides a more detailed picture of changes in core composition, power distributions, and reactivity as a function of time.
- OSTI ID:
- 7231349
- Report Number(s):
- CONF-920606--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 65
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCURACY
ATR REACTOR
COMPUTER CODES
CONTROL ELEMENTS
CONTROL SYSTEMS
COOLING SYSTEMS
ELEMENTS
ENRICHED URANIUM REACTORS
FLUIDS
FUEL ELEMENTS
GASES
IDAHO NATIONAL ENGINEERING LABORATORY
IRRADIATION REACTORS
MATERIALS TESTING REACTORS
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NONMETALS
P CODES
PHYSICS
POWER DENSITY
PRIMARY COOLANT CIRCUITS
PUMPS
RADIATION FLUX
RARE GASES
REACTIVITY
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR PHYSICS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY ANALYSIS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
THREE-DIMENSIONAL CALCULATIONS
TWO-DIMENSIONAL CALCULATIONS
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
XENON
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCURACY
ATR REACTOR
COMPUTER CODES
CONTROL ELEMENTS
CONTROL SYSTEMS
COOLING SYSTEMS
ELEMENTS
ENRICHED URANIUM REACTORS
FLUIDS
FUEL ELEMENTS
GASES
IDAHO NATIONAL ENGINEERING LABORATORY
IRRADIATION REACTORS
MATERIALS TESTING REACTORS
NATIONAL ORGANIZATIONS
NEUTRON FLUX
NONMETALS
P CODES
PHYSICS
POWER DENSITY
PRIMARY COOLANT CIRCUITS
PUMPS
RADIATION FLUX
RARE GASES
REACTIVITY
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR PHYSICS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY ANALYSIS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
THREE-DIMENSIONAL CALCULATIONS
TWO-DIMENSIONAL CALCULATIONS
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
XENON