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Evaluation of cancer risk after a release from a hypothetical nuclear reactor steam generator tube rupture accident (SGTR)

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1 Published in 2020 at "Annals of Nuclear Energy"

DOI: 10.1016/j.anucene.2019.107023

Abstract: Abstract This work aims to model a potential consequence after the release of radioactive material from the inventory of a PWR nuclear reactor in a case of an event known as steam generator tube rupture… read more here.

Keywords: risk; generator tube; steam generator; evaluation ... See more keywords

Realistic evaluation of source terms for steam generator tube rupture accidents

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1 Published in 2021 at "Annals of Nuclear Energy"

DOI: 10.1016/j.anucene.2021.108559

Abstract: Abstract In the existing Probabilistic Safety Assessment (PSA) model, all the Steam Generator Tube Rupture (SGTR) sequences have been assumed to have identical fission product release characteristics without considering the sequences of no source term… read more here.

Keywords: steam generator; evaluation; sgtr; source ... See more keywords

Characteristics of steam generator tube deposits in an operating pressurized water reactor

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0 Published in 2018 at "Journal of Nuclear Materials"

DOI: 10.1016/j.jnucmat.2018.05.001

Abstract: Abstract The objective of this study is to characterize steam generator tube deposits collected from an operating pressurized water reactor. The deposits were mostly composed of magnetite and contained small amounts of trevorite, jacobsite, and… read more here.

Keywords: water reactor; generator tube; operating pressurized; steam generator ... See more keywords

ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions

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1 Published in 2018 at "Nuclear Engineering and Technology"

DOI: 10.1016/j.net.2018.05.002

Abstract: Abstract An experiment was performed for the OECD/NEA ROSA-2 Project with the large-scale test facility (LSTF), which simulated a steam generator tube rupture (SGTR) accident due to a double-ended guillotine break of one of steam… read more here.

Keywords: recovery; code; generator tube; steam generator ... See more keywords

Probabilistic structural integrity assessment for Inconel690 alloy steam generator tube with volume defect

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0 Published in 2020 at "Nuclear Engineering and Design"

DOI: 10.1016/j.nucengdes.2020.110949

Abstract: Abstract Fit for service(FFS) assessment of Steam Generator Tube(SGT) plays a key role in safety operating of Pressurized Water Reactors. Engineering practices have emerged probabilistic method is a powerful tool in reducing redundant safety margin… read more here.

Keywords: generator tube; integrity assessment; structural integrity; steam generator ... See more keywords