MCNP full-core modeling of the advanced test reactor
- 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-; CODEN: TANSAO
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Vol. 68; Conference: American Nuclear Society (ANS) annual meeting, San Diego, CA (United States), 20-24 Jun 1993; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
NEUTRON TRANSPORT
COMPUTERIZED SIMULATION
WATER COOLED REACTORS
ATR REACTOR
BENCH-SCALE EXPERIMENTS
FUEL ELEMENTS
MONTE CARLO METHOD
REACTOR CORES
THREE-DIMENSIONAL CALCULATIONS
CALCULATION METHODS
ENRICHED URANIUM REACTORS
IRRADIATION REACTORS
MATERIALS TESTING REACTORS
NEUTRAL-PARTICLE TRANSPORT
RADIATION TRANSPORT
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
990200 - Mathematics & Computers