Author:
Ghasabian M.,Talebi S.,Safarzadeh O.
Subject
Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering
Reference27 articles.
1. Final Safety Analysis Report on BNPP-1,2003
2. Fuel Performance of Light Water Reactors (Uranium Oxide and MOX);Baron,2019
3. Sensitivity analysis of VERA-CS and FRAPCON coupling in a multiphysics environment;Beck;Ann. Nucl. Energy,2018
4. FRACAS: a subcode for the analysis of fuel pellet-cladding mechanical interaction (No. TREE-NUREG-1028). SEE CODE-9502158 EG and G Idaho, Inc., Idaho Falls (USA);Bohn;Idaho National Engineering Lab,1977
5. Best estimate plus uncertainty analysis of departure from nucleate boiling limiting case with CASL core simulator VERA-CS in response to PWR main steam line break event;Brown;Nucl. Eng. Des.,2016
Cited by
1 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