MCNP full-core modeling of the advanced test reactor
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:5882147
- Idaho National Engineering Lab., Idaho Falls (United States)
A full-core Monte Carlo neutron and photon (MCNP) transport model has been completed for the advanced test reactor (ATR) at Idaho National Engineering Laboratory. This new model is a complete three-dimensional model that represents fuel elements, core structures, and target regions in adequate detail. The model can be used in evaluating heating and reaction rates in various target regions of the core. This model is especially useful in physics analysis of an asymmetric experiment loading in the core. The ATR is a light-water-cooled thermal reactor with aluminum/uranium-aluminide fuel plates grouped in arcuate fuel elements that form a serpentine arrangement, as shown in Fig. 1. The core is surrounded by a beryllium reflector. Nine test loops are nestled in the lobes of the serpentine core, and numerous other irradiation holes with varying dimensions and radiation environments are located in the reflector and in the core interior.
- OSTI ID:
- 5882147
- Report Number(s):
- CONF-930601--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 68
- 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
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ATR REACTOR
BENCH-SCALE EXPERIMENTS
CALCULATION METHODS
COMPUTERIZED SIMULATION
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
IRRADIATION REACTORS
MATERIALS TESTING REACTORS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
RADIATION TRANSPORT
REACTOR COMPONENTS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
THREE-DIMENSIONAL CALCULATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ATR REACTOR
BENCH-SCALE EXPERIMENTS
CALCULATION METHODS
COMPUTERIZED SIMULATION
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
IRRADIATION REACTORS
MATERIALS TESTING REACTORS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
RADIATION TRANSPORT
REACTOR COMPONENTS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
THREE-DIMENSIONAL CALCULATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS