The　fluoride-salt-cooled　high-temperature　reactor　(FHR)　is　a　Generation　IV　nuclear　energy　system　with　huge　potential　for　further　development.　Owing　to　its　unique　advantages,　such　as　inherent　safety,　high　economical　potential,　small　modular　design,　environmental　adaptability,　and　nonproliferation,　FHRs　have　been　the　focus　of　considerable　attention.　In　this　study,　the　history　and　characteristics　of　FHR　are　reviewed　first,　including　the　concept　initiation　and　active　exploration　stages.　Then,　the　research　status　of　FHR　is　introduced,　which　is　about　the　state　of　the　art　in　primary　coolant　systems,　structural　materials,　key　equipment,　energy　conversion　systems,　direct　reactor　auxiliary　cooling　systems,　nuclear　fuel,　tritium　control　strategies,　and　experimental　studies.　Furthermore,　the　challenges　faced　by　FHR　technology　are　summarized,　including　corrosion　of　structural　materials,　optimization　of　energy　conversion　systems,　solidification　of　fluoride　salts,　control　of　tritium,　control　of　beryllium　contamination,　enrichment　of　lithium　fluoride-beryllium　fluoride　salt,　design　of　core　refueling,　and　operation　and　control　of　pebble　bed　reactor.　Based　on　the　above,　the　focuses　of　research　on　FHR　design　are　discussed,　and　areas　of　study　for　future　development　of　FHR　technology　are　recommended.　This　paper　aims　to　provide　a　reference　for　the　research　and　development　of　FHR　in　the　future.