DESIGN OF A TRISO PARTICLE FUEL BASED INTEGRATED GAS-COOLED SPACE NUCLEAR REACTOR

Li Zeguang,Shi Lei,Sun Jun,Liu Malin,Lang Minggang,Yang Xiaoyong,M Margulis,P Blaise

doi:10.1051/epjconf/202124701001

Abstract

According to versatile and long-lasting requirements of deep space missions, space nuclear reactor (SNR) power system is becoming a more suitable choice compared to traditional solar and chemical power systems in large-scale and long-life applications. From NASA’s previous research, the gas-cooled reactor along with closed Brayton cycle (CBC) could achieve optimized weight-power ratio and be more applicable for large power system (100 kWe or MWe level). In this paper, a concept of integrated gas-cooled space nuclear reactor named IGCR-200 is introduced, which is designed based on the TRISO particle fuel and could achieve 200 kWe output combined with highly efficient He/Xe CBC generator. The design requirements include an operation lifetime of at least 10 years in full power mode, maximum fuel temperature < 1600K, negative temperature reactivity feedback, passive decay heat removal, redundancy in reactor control, and sub-criticality during water flooding accidents. It has an outer diameter of 70.0 cm, a height of 66.0 cm (reactor part), a total mass around 1000 kg, total Uranium inventory of 226.8 kg (235U enrichment as 93%), and 1 MW thermal power output. The reactor physics, thermal hydraulics and other required analysis are taken out to show the feasibility and performances of the design.

Highlights

The nuclear energy in space has been considered as a good option to provide steady and long-lasting electricity supply, especially in situations when and where the solar option is inadequate, impractical, or nonexistent [1]
A concept of integrated gas-cooled space nuclear reactor (SNR) named IGCR-200 is proposed, which is designed based on the TRISO particle fuel and could achieve 200 kWe output power combined with highly efficient He/Xe closed Brayton cycle (CBC) power conversion units (PCUs) [7]
The neutronics analyses described are performed using the Monte Carlo code RMC [10][11], and a set of continuous energy cross-section libraries from the ENDF-B VII.1 nuclear data was used in the analyses

Summary

Introduction

The nuclear energy in space has been considered as a good option to provide steady and long-lasting electricity supply, especially in situations when and where the solar option is inadequate, impractical, or nonexistent [1]. The Institute of Nuclear and New Energy Technology (INET) at Tsinghua University has accumulated a lot of research experiences in TRISO particle fuel, inert gas process and direct Brayton cycle conversion system [6], which are the most important aspects in large-scale gas-cooled SNR design. The reactor has an outer diameter of 70.0 cm, a height of 66.0 cm (core part), a total mass around 1000 kg, total Uranium inventory of 226.8 kg (235U enrichment as 93%), and 1.0 MW thermal power output

Methods

Results

Conclusion