Overview

KAMPS is primarily applied in multi-physics and multi-scale nuclear reactor analysis, enabling high-fidelity simulations that combine thermal-hydraulics, neutronics, and core-level or plant-level dynamics.

Selected cases for nuclear safety analysis

The KAMPS platform has been applied in several coupled simulations, primarily within the European McSAFER project. This project focuses on the multi-physics-scale analysis of Small Modular Reactors (SMRs), particularly the SMART reactor.

Key accident scenarios such as the Steam Line Break (SLB) and Rod Ejection Accident (REA) have been simulated using various coupling configurations. The platform is also extended to large-scale reactors like VVERs.

1) TRACE / PARCS / SCF Coupling for SLB in SMART Reactor

(Smart) (Steam Line Break - SLB)

Configuration

TRACE handles system thermal-hydraulics (excluding core)
SCF handles core thermal-hydraulics
PARCS handles core neutronics

Interfaces: Two 2D coupling interfaces (TRACE–SCF) + one 3D interface (SCF–PARCS)

The coolant temperature at the beginning of the SLB transient

The coolant temperature at the end of the SLB transient

Simulation Summary: Double-ended steam line break leading to rapid pressure drop, reactor SCRAM, loss of offsite power, and natural circulation establishment with PRHRS activation.

The mass flow evolution during the SLB in the SMART reactor

2) TRACE/PARCS/TPF Coupling for SLB in SMART Reactor

(Smart) (Steam Line Break - SLB)

Configuration

TRACE handles system thermal-hydraulics
TPF handles core thermal-hydraulics (replacing SCF)
PARCS handles core neutronics

Interfaces: Two 2D planes (TRACE–TPF) + one 3D interface (TPF–PARCS)

Simulation Summary: Consistent SLB evolution results with SCF case, demonstrating platform flexibility to switch between different TH solvers.

3) TRACE/PARCS/OpenFOAM Coupling for SLB in SMART Reactor

(Smart) (Steam Line Break - SLB)

Configuration

TRACE simulates system (except downcomer and lower plenum)
TrioCFD simulates downcomer and lower plenum
PARCS performs core neutronics

Interfaces: Two 2D interfaces (TRACE–TrioCFD) + one 3D interface (TRACE–PARCS)

Simulation Summary: Rapid depressurization and SCRAM with natural circulation and PRHRS activation, showcasing CFD-system code viability.

4) PARCS/SCF Pin-Level REA in SMART Reactor

(Smart) (Rod Ejection Accident - REA)

Configuration

PARCS simulates core neutronics at pin level
SCF simulates core thermal-hydraulics
Extended PARCS with nodal solver for pin-level resolution

Power evolution during the REA transient

Interfaces: Full 3D core coupling with cross-sections from Serpent + SPH factors

Simulation Summary: Sudden ejection of most reactive control rod causing rapid power increase, then reduction to ~20% nominal due to thermal feedback.

5) SERPENT/SUBCHANFLOW ICoCo-Based Coupling for High-Fidelity Core Simulations

(LWRs, SMRs – Steady-State, Transients, and Depletion)

Configuration

Serpent2 performs Monte Carlo neutron transport simulations
SUBCHANFLOW (SCF) models core-level subchannel thermal-hydraulics
Coupling based on the ICoCo interface using an object-oriented C++ supervisor
Mesh-based feedback exchange with MEDCoupling interpolation

Interfaces

Full-core pin-by-pin neutronic ↔ thermal-hydraulic coupling
Multi-mesh system: separate unstructured meshes for coolant and fuel
Semi-implicit feedback scheme ensuring convergence at each burnup step

Simulation Summary: The Serpent2–SUBCHANFLOW coupling enables high-fidelity simulations of light water reactors (PWR, VVER, SMR) by combining Monte Carlo neutronics with detailed subchannel-level thermal-hydraulics. Applicable to steady-state, depletion, and transient analyses, the system has been validated through experimental benchmarks (e.g., VERA, SPERT IV, MTRs).