7   Artículos

 
en línea
Stefan Ritter and Hans-Peter Seifert    
Low-alloy reactor pressure vessel steels have a rather low susceptibility to stress corrosion cracking (SCC) in a boiling water reactor (BWR) environment if the high-temperature water contains no anionic impurities. Recent investigations revealed that un... ver más
Revista: Corrosion and Materials Degradation    Formato: Electrónico

 
en línea
Digby D. Macdonald and George R. Engelhardt    
The radiolysis of water is a significant cause of corrosion damage in the primary heat transport systems (PHTSs) of water-cooled, fission nuclear power reactors (BWRs, PWRs, and CANDUs) and is projected to be a significant factor in the evolution of corr... ver más
Revista: Corrosion and Materials Degradation    Formato: Electrónico

 
en línea
Digby D. Macdonald, George R. Engelhardt and Andrei Petrov    
A critical review is presented on modeling of the radiolysis of the coolant water in nuclear power reactors with emphasis on ITER. The review is presented in two parts: In Part I, we assess previous work in terms of compliance with important chemical pri... ver más
Revista: Corrosion and Materials Degradation    Formato: Electrónico

 
en línea
Vitaliy Galchenko,Vladyslav Soloviov     Pág. 1 - 4
Using a burnup credit as safety criteria in a spent nuclear fuel (SNF) criticality calculations required accuracy isotopes composition preparation approach. Comparisons between calculation results and existing experimental data are one effective way for ... ver más
Revista: International Nuclear Safety Journal    Formato: Electrónico

 
en línea
Abdul Wasay Khan     Pág. 1 - 8
This paper presents an examination of the consequences of a hypothetical failure of the Residual Heat Removal (RHR) system during the shutdown operating mode, in a two loops Pressurized Water Reactor (PWR).The purpose of the analyses presented in this pa... ver más
Revista: International Nuclear Safety Journal    Formato: Electrónico

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