MCNP full-core modeling of the advanced test reactor
Creators
- 1. Idaho National Engineering Lab., Idaho Falls (United States)
Description
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
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 68
- Journal Page Range
- p. 434.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- American Nuclear Society (ANS) annual meeting.
- Dates
- 20-24 Jun 1993.
- Place
- San Diego, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25022833
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATR REACTOR; BENCH-SCALE EXPERIMENTS; COMPUTERIZED SIMULATION; FUEL ELEMENTS; MONTE CARLO METHOD; NEUTRON TRANSPORT; REACTOR CORES; THREE-DIMENSIONAL CALCULATIONS; WATER COOLED REACTORS
- Descriptors DEC
- 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 FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-930601--.