Numerical simulation on the thermal stratification in the lead pool of lead-cooled fast reactor (LFR)-Reference-Cited by-同舟云学术

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Numerical simulation on the thermal stratification in the lead pool of lead-cooled fast reactor (LFR)

Published:2022-09 Issue: Volume:174 Page:109176
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Dong Zhengyang,Qiu Hanrui,Wang Mingjun,Tian Wenxi,Qiu Suizheng,Su G.H.

Funder

National Natural Science Foundation of China

China Academy of Space Technology

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference32 articles.

1. Recent progress of CFD applications in PWR thermal hydraulics study and future directions;Wang;Annals of Nuclear Energy,2021

2. Numerical study on the thermal stratification characteristics in the upper plenum of sodium-cooled fast reactor (SFR);Wang;Annals of Nuclear Energy,2020

3. Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors;Song;Progress in Nuclear Energy,2019

4. Improvement and evaluation of ATWS Protective Signal and mitigation system for ACPR1000 nuclear power plant;Zhang;International Journal of Advanced Nuclear Reactor Design and Technology,2022

5. CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for sodium-cooled fast reactor;Chen;Annals of Nuclear Energy,2018

Cited by 15 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Numerical study on the characteristics of the LBE thermal stratification in a scaled-down hot pool;Annals of Nuclear Energy;2025-02

2. Study on the safety performance of an offshore stationary lead-cooled fast reactor design loaded with nitride fuel;Annals of Nuclear Energy;2024-12

3. Thermal-hydraulic analysis of a full-scale lead-bismuth cooled fast reactor core considering inter-wrapper flow;Progress in Nuclear Energy;2024-10

4. Application of BPNN algorithm in thermal-hydraulic analysis of unwrapped LFR core;International Journal of Thermal Sciences;2024-09

5. Research on fine analysis and accelerated prediction technology for thermal stratification in the upper plenum of the “Monju” reactor;Case Studies in Thermal Engineering;2024-08

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