Research on thermal behaviors of several accident tolerant fuels based on 5 × 5 bundle subchannel model-Reference-Cited by-同舟云学术

Research on thermal behaviors of several accident tolerant fuels based on 5 × 5 bundle subchannel model

Published:2019-11 Issue: Volume:133 Page:9-20
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Cai Jiejin^ORCID,Chen Zhijie,He Sihong,Liu Rong

Funder

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference37 articles.

1. Assessment of CTF Boiling Transition and Critical Heat Flux Modeling Capabilities Using the OECD/NRC BFBT and PSBT Benchmark Databases;Avramova;Sci. Technol. Nucl. Install.,2013

2. Thermo-mechanical analysis of LWR SiC/SiC composite cladding;Ben-Belgacem;J. Nucl. Mater.,2014

3. Preliminary thermal hydraulic analysis of various accident tolerant fuels and claddings for control rod ejection accidents in LWRs;Chen;Nucl. Eng. Des.,2018

4. Oxidation of fuel cladding candidate materials in steam environments at high temperature and pressure;Cheng;J. Nucl. Mater.,2012

5. Safety evaluation of accident-tolerant FCM fueled core with SiC-coated zircalloy cladding for design-basis-accidents and beyond DBAs;Chun;Nucl. Eng. Des.,2015

Cited by 6 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. Subchannel thermal hydraulic analysis of 5 × 5 rod bundle with CRUD layer;Nuclear Engineering and Design;2023-08

2. Effect of thermo-physical properties of accident tolerant fuels on transient fuel behaviors and the safety;Annals of Nuclear Energy;2022-07

3. Core analysis of accident tolerant fuel cladding for SMART reactor under normal operation and rod ejection accident using DRAGON and PARCS;Nuclear Engineering and Technology;2021-03

4. Accident tolerant fuel thermal hydraulic behaviors evaluation during loss of coolant accident in CPR1000;Annals of Nuclear Energy;2020-05

5. Thermal hydraulic analysis of the PWR with high uranium density accident tolerant fuels under accident transients with and without reactivity;Nuclear Engineering and Design;2019-12