Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Implementation of an Orificing Optimization Algorithm in the DASSH Subchannel Analysis Code

Technical Report ·
DOI:https://doi.org/10.2172/1896893· OSTI ID:1896893
 [1];  [1]
  1. Argonne National Laboratory (ANL), Argonne, IL (United States)
The Ducted Assembly Steady-State Heat transfer code (DASSH) performs full-core subchannel thermal hydraulics calculations in liquid metal fast reactors. One of the applications of subchannel codes is to optimize coolant flow orificing. As a design activity, the primary task is to determine the best way to divide assemblies into groups and distribute coolant flow rates among them. This report documents an algorithm implemented in DASSH to automatically optimize coolant orificing. Over the course of multiple iterations, DASSH determines the orifice grouping and flow distribution that minimizes peak coolant, clad, or fuel temperatures across all timesteps for a user-specified number of assembly groups. The total coolant flow rate in the reactor is constrained to achieve the specified core-average outlet temperature. The flow rate to each orifice group may also be constrained by the allowable pressure drop. The distribution of coolant flow among groups is accelerated using a predictor-corrector algorithm based on interpolated results from single-assembly parametric calculations. The assembly orificing grouping is initially predicted based on assembly power but can be refined if results demonstrate that an assembly would fit better in another group. The algorithm is demonstrated with two case studies. The first is a simple model for a reactor core consisting of just fuel assemblies; the pin power distributions are specified to create a situation where the initial assembly grouping prediction is suboptimal. This example is used to describe the initial grouping, demonstrate convergence over multiple iterations, and highlight the impact of regrouping. Then, the algorithm is applied to minimize peak clad and fuel temperatures in an example sodium-cooled fast reactor, the Versatile Test Reactor. The multicycle optimization confirms prior calculations for the reference core design. The example highlights how optimizing for different peak temperatures affects the results and demonstrates the use of the pressure drop constraint to limit the maximum flow rate.
Research Organization:
Argonne National Laboratory (ANL), Argonne, IL (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
DOE Contract Number:
AC02-06CH11357
OSTI ID:
1896893
Report Number(s):
ANL-VTR-104; 178011
Country of Publication:
United States
Language:
English

Similar Records

DASSH-F: Subchannel Based Thermal Analysis
Technical Report · Sun Dec 29 23:00:00 EST 2024 · OSTI ID:2506724

Flow orificing of large LMFBR cores with interassembly heat transfer
Conference · Fri Dec 31 23:00:00 EST 1976 · OSTI ID:5023933

Summary of DASSH-CFD Inter-Assembly Heat Transfer Comparison
Technical Report · Tue Aug 10 00:00:00 EDT 2021 · OSTI ID:1906276