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Theodore Kay Chen Ong

Publications and source records attributed to Theodore Kay Chen Ong.

2 recordsLinked to original sources

Agentic Porting, Construction and Initial Verification and Validation of Libraries within the Open Source Unified TRAnsient Multi-Phase Advanced Reactor simulation Kit (Outram Park) Part I: A Software Engineering Log for Thermal Hydraulics

Agentic porting of multiple open-source libraries into Rust, with human in the loop, has been performed for construction of modules within the Open-source Unified TRAnsient Multi-Phase Advanced Reactor simulation Kit (Outram Park). With this new methodology, verification and validation with human expertise, rather than code generation, has become the bottleneck in developing reliable simulation codes. In this work, we present the porting of OpenFOAM libraries into the Outram-Foam Rust libraries, their preliminary verification and validation (V&V) efforts, and their subsequent use in the development of open-source two-phase homogeneous-equilibrium (HEM) choked-flow solvers for the Thermo-hydraulic AI Multi-Phase INtegrated Emulator System (TAMPINES) libraries within Outram Park, such as tampines-steam-tables. V&V efforts of Outram-Foam show that the cavity and Sod shock tube cases agree with literature values to within acceptable margin. Moreover, the preliminary development of tampines-steam-tables shows good agreement with Moody's HEM charts. Thereafter, the 1D HEM solver, developed agentically, is presented and preliminarily validated against the Edwards blowdown case. Productivity increases were observed with the use of Claude Code, but domain expertise supplied by human experts remains critically required to ensure the generated code can solve the problem effectively. Further work remains to be done in V&V, but the agentic coding methodology described here demonstrates considerable potential to speed up production and development of open-source libraries such as Outram Park.

physics.comp-ph↗

Agentic Porting, Construction and Initial Verification and Validation of Libraries within the Open Source Unified TRAnsient Multi-Physics Advanced Reactor simulation Kit (Outram Park) Part II: Nuclear Data and Neutronics

An agentic Rust port of both Njoy and OpenMC components was attempted to produce a convenient ENDF to Monte Carlo simulation pipeline in Outram Park. The code is still a prototype with more extensive verification and validation studies required in future studies. For initial verification work, Doppler-broadened cross sections of U-238 are demonstrated in this paper and compared to OpenMC pre-generated HDF5 files. Additionally, initial testing of the Monte Carlo ports from OpenMC were also performed with ICSBEP benchmarks and a FHR Pebble with TRISO Fuel used in the author's PhD dissertation. The addition of nuclear data and Monte Carlo case studies shifts the focus of Outram Park from a Multi-Phase simulation kit to a Multi-Physics simulation kit.

physics.comp-ph↗