Abstract

In order to meet modern industrial and scientific demands the Kraken multi-physics platform’s development was recently launched at VTT Technical Research Centre of Finland. The neutronic solver of the framework consists of two calculation chains, providing full core solutions by the Serpent high fidelity code (1) and the AFEN/FENM-based reduced-order diffusion solver called Ants (2) capable of handling square and hexagonal geometries in steady-state. Present work introduces the simulation of a large 3600 MWth Sodium-cooled Fast Reactor (SFR) described within the activities of the Working Party on Scientific Issues of Reactor Systems (WPRS) of OECD. Full-core 3D results were obtained by Serpent for carbide- and oxide-fuel cores, moreover group constants were generated for Ants utilizing 2D super-cell and single assembly infinite lattice models of Serpent. The continuous-energy Monte Carlo method provided the reference results for the verification of the reduced-order method. Implementing the spatially homogenized properties, 3D solutions were obtained by Ants as well for both core configurations. Comparison was made between the various core designs and codes based on reactivity feedbacks (Doppler constant, sodium voiding, control rod worth) considering power distributions. Regarding reactivity sensitivity on geometry, axial fuel- and radial core expansion coefficients were evaluated as well.

Highlights

  • Benchmark data from report [1] was used to construct 3D full-core Sodium-cooled Fast Reactor (SFR) models in Serpent with respect to given boundary conditions

  • Full-core 3D model inputs were built for Serpent 2.1.31 [2] based on Ref. [1] whereas He pressure was chosen to be 10 bar according to MOX fuel recommendations reported by the Halden Reactor Project [3]

  • Results were compared with benchmark data summarized in [6] and studies conducted by Nikitin et al [7,8] with Serpent

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Summary

INTRODUCTION

Benchmark data from report [1] was used to construct 3D full-core SFR models in Serpent with respect to given boundary conditions. One of carbide (CA) and one of oxide (OX) fuel was defined with Beginning of Cycle (BoC) isotopic composition. The assessment of Ants will be carried out with respect to 3D Serpent results

SERPENT FULL-CORE 3D MODELS
Core Configurations
Present Models
Serpent Results
FEW-GROUP CONSTANTS’ GENERATION FOR ANTS
Few-Group Cross Section Generation Sensitivity Study
Code and Input Structure
Comparison of Ants and Serpent
CONCLUSIONS
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