Main steam line break analysis in 2775 MWth PWR reactor core
Joint Authors
Source
Arab Journal of Nuclear Sciences and Applications
Issue
Vol. 50, Issue 3 (31 Jul. 2017), pp.186-196, 11 p.
Publisher
The Egyptian Society of Nuclear Science and Applications
Publication Date
2017-07-31
Country of Publication
Egypt
No. of Pages
11
Main Subjects
Topics
Abstract EN
This study aims to analyze the effects of accident of Main Steam Line Break (MSLB) for a three-loop Reactor, 2775 MWth PWR, where it can cause potential reactivity insertion accidents (RIA).
Multi-group diffusion depletion 3D code TRITON was used to calculate both the neutron flux and the power density distributions, depending on the cross sections at the beginning of cycle conditions, in the normal case, and in case of temperature decrease as a result of this accident.
The thermal-hydraulic calculations were carried out using a MATLAB script written to fit the power density values and to calculate the coolant temperature distribution inside the core.
American Psychological Association (APA)
Isa, M.& Najla, T.& Badawi, A.. 2017. Main steam line break analysis in 2775 MWth PWR reactor core. Arab Journal of Nuclear Sciences and Applications،Vol. 50, no. 3, pp.186-196.
https://search.emarefa.net/detail/BIM-760062
Modern Language Association (MLA)
Isa, M.…[et al.]. Main steam line break analysis in 2775 MWth PWR reactor core. Arab Journal of Nuclear Sciences and Applications Vol. 50, no. 3 (Jul. 2017), pp.186-196.
https://search.emarefa.net/detail/BIM-760062
American Medical Association (AMA)
Isa, M.& Najla, T.& Badawi, A.. Main steam line break analysis in 2775 MWth PWR reactor core. Arab Journal of Nuclear Sciences and Applications. 2017. Vol. 50, no. 3, pp.186-196.
https://search.emarefa.net/detail/BIM-760062
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references : p. 195-196
Record ID
BIM-760062
