Defining the performance envelope of reactivity-initiated accidents in a high-temperature gas-cooled reactor

Jacob P. Gorton, Nicholas R. Brown

Research output: Contribution to journalArticlepeer-review

16 Scopus citations

Abstract

The purpose of this study is to define an envelope of possible transient conditions during two reactivity-initiated accidents (RIAs) in a modular high-temperature gas-cooled reactor (mHTGR). The accident scenarios studied were a group control rod withdrawal (CRW), a design basis accident, and a control rod ejection (CRE), a beyond design basis accident. Variance-based sensitivity analysis methods were employed to obtain realistic bounds on the reactor power and maximum temperature, energy deposition, and heating rate in the fuel during these accidents. Key reactor kinetic parameters and the heat transfer properties of the fuel and moderator were varied in a RELAP computer model of a 350-megawatt mHTGR to obtain these bounds. Sobol sensitivity indices were calculated to highlight which inputs account for the most variance in the outputs. Results showed that the kinetic properties and reactivity temperature coefficients were the most dominant inputs, while thermal properties had little impact on the outputs. Compared to previous experimental work, the fuel particle energy deposition from the simulated RIAs would not be expected to cause fuel failure in any design basis or beyond design basis reactivity accident we investigated. The predicted energy deposition in fuel kernels ranged from 98 to 331 J/g-fuel, significantly less than the expected failure threshold of approximately 1500 J/g-fuel. However, the power pulse widths and heating rates used in previous fuel safety experiments were different from the values predicted in this study for both accident scenarios. Regardless of these differences, this analysis shows that the safety margins in graphite-moderated mHTGRs for reactivity accidents are very large, and additional fuel safety tests are not expected to be necessary for this application.

Original languageEnglish
Article number110865
JournalNuclear Engineering and Design
Volume370
DOIs
StatePublished - Dec 15 2020
Externally publishedYes

Funding

This research work was mostly financially unsupported. The methodology development was partially supported by the Advanced Research Projects Agency – Energy (ARPA-E) Modeling Enhanced Innovations Trailblazing Nuclear Energy Reinvigoration (MEITNER) program under contract DE-AR000087.

FundersFunder number
ARPA-E) Modeling Enhanced Innovations Trailblazing Nuclear Energy Reinvigoration
MEITNERDE-AR000087
Advanced Research Projects Agency - Energy

    Keywords

    • Fuel safety
    • RIA
    • Transient TRISO
    • mHTGR

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