Abstract

One of the benefits of the supercritical CO 2 Brayton cycle in Sodium-cooled Fast Reactors is an enhanced plant safety, since potential reactions of CO 2 with liquid sodium have been reported to be less stringent than a sodium-water reaction found in the Rankine cycle. However, moderate chemical interactions between CO 2 and liquid sodium make detecting CO 2 ingress accidents harder. Thus, this paper proposes a new physics-based detection algorithm by comparing the real-time pressure measurements of two identical heat exchangers for the early detection. The CO 2 ingress occurs owing to a crack at the pressure boundary wall, a certain self-recovery of structural damage does not happen over time, and an accident probabilistically starts at only one component of two. The proposed physics-based method with the probabilistic analysis was compared to the pure data-based method. Finally, the damage degradation was developed with a simplified mass and energy transfer model, and the proposed algorithm was verified with experimental data. The results show that a 99.99% detection probability can be achieved for the air ingress of 30 cc/s, which is equivalent to the 0.12 g/s CO 2 ingress, in a 70 s detection time, limiting down to 0.1% false alarms due to sensor noise.

Highlights

  • A Sodium-cooled Fast Reactor (SFR) is one of the Generation IV (Gen-IV) nuclear fission reactors [1]

  • The Gen-IV reactors are categorized to achieve a number of design goals: improved safety, sustainability, efficiency, cost, and proliferation resistance [2,3]

  • The goal of this study is to bring about a mathematical framework, introduced in Section 3, for a condition based monitoring (CBM) system based on physics to automatically depressurize the steam side, and disconnect the CO2 gas supply by detecting localized sodium-CO2 events in Sodium-to-Gas Heat Exchanger (SGHX)

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Summary

Introduction

A Sodium-cooled Fast Reactor (SFR) is one of the Generation IV (Gen-IV) nuclear fission reactors [1]. The Gen-IV reactors are categorized to achieve a number of design goals: improved safety, sustainability, efficiency, cost, and proliferation resistance [2,3]. SFR is a fast neutron reactor, utilizing sodium as a coolant. The inherent passive safety of fast reactors, safely shutting itself down, is one of the advantages expected by the Gen-IV reactors. Sodium melts at a low temperature (98 ◦ C), and the boiling temperature is greater than 800 ◦ C. This property fits very well in a typical operating range of SFRs (300∼550 ◦ C)

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