Download Intro_RAST-K 3.0
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Introduction
The nodal diffusion code RAST-K is the second part of
a conventional two-step approach code system, which is developed by
UNIST CORE laboratory and sponsored by Korea Hydraulic & Nuclear
Power Co. Ltd.. To achieve high accuracy of reactor analysis with
affordable memory requirement and computing time, the pin-by-pin kernel
is newly implemented in RAST-K v3. The neutron transport calculation is
performed by solving pin-by-pin SP3 equation with axially
unified nodal method. The pin-wise cross section data is corrected by
SPH factor to preserve the accuracy of transport calculation. The
depletion, TH feedback, and cross section feedback modules and
user-supporting engineering features for convenience of reactor core
design and analysis are extended from the sub-assembly to sub-pin level.
The parallel computing capability is also applied to pin-by-pin kernel
with high computing resources.
Physics ModelNeutronics - Multi-group pin-wise SP3 XS model - Eight-group group constants from STREAM2D TH feedback - Single phase formulation (no boiling) without momentum equation (constant pressure) Fuel cycle analysis - Micro-depletion for 22 actinides and 12 fission products Domain DecompositionAll processor need to have …
Verification- OPR1000 cycle 1 whole core depletion
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4. Code Development >