Abstract

China Experimental Fast Reactor (CEFR) is a small size sodium-cooled fast reactor (SFR) with a high neutron leakage core fueled by uranium oxide. The CEFR core with 20 MW(e) power reached its first criticality in July 2010, and several start-up tests were conducted from 2010 to 2011. The China Institute of Atomic Energy (CIAE) proposed to release some of the neutronics start-up test data for the IAEA benchmark within the scope of the IAEA’s coordinated research activities through the coordinated research project (CRP) on “Neutronics Benchmark of CEFR Start-Up Tests”, launched in 2018. This benchmark aims to perform validation and verification of the physical models and the neutronics simulation codes by comparing calculation results against collected experimental data. The six physics start-up tests considered for this CRP include evaluation of the criticality, control rod worth, void reactivity, temperature coefficient, swap reactivity, and foil irradiation. Twenty-nine participating research organizations are performing independent blind calculations during the first phase of the project. As a part of this coordinated research, IAEA performed neutronics calculations using Monte Carlo code SERPENT. Two kinds of 3D core models, homogenous and heterogeneous, were calculated using SERPENT, with ENDF/B-VII.0 continuous energy library. Preliminary results with a reasonably good estimation of criticality, as well as theoretically sound results of other five test cases, are available. The paper will discuss the core modelling assumptions, challenges and key findings of modelling a dense SFR core, preliminary results of the first phase of the CRP, heterogeneity impact analysis between homogenous core models and heterogeneous core models and future work to be performed as a part of this four-year project.

Highlights

  • Many fast reactors (FRs) experiments have been carried out for several decades in various countries [2]; only a few neutronics benchmarks are available [3]

  • The paper will discuss the core modelling assumptions, challenges of modelling a dense sodium-cooled fast reactor (SFR) core, the impact of heterogeneity, preliminary results of the first phase of this coordinated research https://doi.org/10.1051/epjconf/202124710008 project (CRP), and future work to be performed as a part of this four-year project

  • It is a crucial benchmark exercise for validation of physical and mathematical neutronics models implemented in SFR simulation codes, which will help in reducing uncertainty in modelling of neutronics in fast reactors

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Summary

INTRODUCTION

Many fast reactors (FRs) experiments have been carried out for several decades in various countries [2]; only a few neutronics benchmarks are available [3]. This benchmark aims to perform validation and verification of the physical models and the neutronics simulation codes by comparing calculation results against collected experimental data. The paper will discuss the core modelling assumptions, challenges of modelling a dense SFR core, the impact of heterogeneity, preliminary results of the first phase of this CRP, and future work to be performed as a part of this four-year project It is a crucial benchmark exercise for validation of physical and mathematical neutronics models implemented in SFR simulation codes, which will help in reducing uncertainty in modelling of neutronics in fast reactors

MODELLING CEFR BENCHMARK
BENCHMARK RESULTS
Control Rod Worth
Temperature Coefficients
Void Worth
Swap Reactivity
CONCLUSIONS
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