Results 11 to 20 of about 25 (21)

Neutronic design study of a small modular IPWR loaded with accident tolerant-fully ceramic micro-encapsulated (AT-FCM) fuel

Nuclear Engineering and Design, 2018
M Qasim Awan, Liangzhi Cao, Hongchun Wu   +2 more
exaly  

Calculation analysis on the natural circulation of a passive residual heat removal system for IPWR

Annals of Nuclear Energy, 2014
Genglei Xia, Minjun Peng, Xue Du
exaly  

Study on natural circulation characteristics of an IPWR under inclined and rolling condition

Nuclear Engineering and Design, 2017
Genglei Xia, Minjun Peng
exaly  

Neutronic/thermal-hydraulic coupling analysis of natural circulation IPWR under ocean conditions

Annals of Nuclear Energy, 2018
Genglei Xia, Xue Du, Chenyang Wang
exaly  

Simulation of Loss of Coolant Accident in an Integral Pressurized Water Reactor (IPWR)

Advanced Materials Research, 2011
Muhammad Zubair
exaly  

Risk identification of integral pressurized water reactor (IPWR) cooling system using a combination HAZOP, FMEA, and FTA methods

Process Safety Progress
Deswandri Deswandri, Ibnu Maulana Hidayatullah, Muhamad Sahlan   +2 more
exaly  

MELCOR 2.2 iPWR LOCA type accident analysis, PART I: Thermal-hydraulics

Nuclear Engineering and Design
Mateusz Malicki, Terttaliisa Lind
exaly  

MELCOR model of iPWR and application to emergency planning zone study

Nuclear Engineering and Design
Luke Lebel, Andrew Morreale, David Hummel   +2 more
exaly  

MELCOR 2.2 iPWR LOCA type accident analysis, PART II: BDBA

Nuclear Engineering and Design
Mateusz Malicki
exaly  

Safety Analysis for IPWR under Over-Pressurizing Accident Conditions

2010
Minjun Peng
exaly