Thermal hydraulic safety characteristics analysis for the natural circulation primary loop under inclined condition on LFR

Lead-cooled fast reactor (LFR) has been an important option for floating nuclear power plant. The design of 50 MW natural circulation LFR had been proposed by Lanzhou University for floating nuclear power plant. However, floating nuclear power plant was affected by the marine environment, which led...

Full description

Saved in:
Bibliographic Details
Main Authors: Jinting Liu, Tingyu Li, Yang Li, Danna Zhou, Dajian Yu
Format: Article
Language:English
Published: Frontiers Media S.A. 2025-05-01
Series:Frontiers in Energy Research
Subjects:
Online Access:https://www.frontiersin.org/articles/10.3389/fenrg.2025.1566271/full
Tags: Add Tag
No Tags, Be the first to tag this record!