Abstract
Molten salt reactor (MSR) adopts molten fluoride salt mixture as fuel and coolant, and the features of neutronics and thermal-hydraulics of MSR are different from those of traditional solid-fuel reactors due to flowing fuel. Steady state analysis of a preliminary design of thorium molten salt reactor (TMSR) was performed based on MSR analysis code MOREL2.0. The results show that fuel flow brings a significant influence on the distribution of delayed neutron precursors and leads to 169 pcm of reactivity loss, k eff decreases as the increase of time spent through external loop and tends to be stable after 80 s, and TMSR has a negative inlet fuel temperature coefficient and inherent safety characteristic.
| Translated title of the contribution | Steady Analysis of Graphite-moderator Molten Salt Reactor Based on MOREL2.0 |
|---|---|
| Original language | Chinese (Traditional) |
| Pages (from-to) | 1774-1779 |
| Number of pages | 6 |
| Journal | Yuanzineng Kexue Jishu/Atomic Energy Science and Technology |
| Volume | 52 |
| Issue number | 10 |
| DOIs | |
| State | Published - 20 Oct 2018 |