Evaluation of CANDU NPP containment structure subjected to aging and internal pressure increase
Sign Up to like & getrecommendations! Published in 2017 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2017.01.013
Abstract: Abstract The objective of this study is to investigate the long-term performance of a typical CANDU® 1 containment structure. A three-dimensional nonlinear finite element model was built to realistically evaluate the performance of the structure… read more here.
Keywords: candu; containment structure; structure; internal pressure ... See more keywords
Fluid flow in a diametrally expanded CANDU fuel channel – Part 1: Experimental study
Sign Up to like & getrecommendations! Published in 2020 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2019.110371
Abstract: Abstract The overall aim of this study is to develop and validate experimental and computational capabilities to provide high-resolution isothermal fluid velocity data for nuclear reactor investigations. The current work presents full-field velocity data in… read more here.
Keywords: fuel channel; part; candu; velocity ... See more keywords
Best-estimate severe accident and source term analysis for an ISLOCA scenario of a CANDU-6 plant using the MAAP-ISAAC code
Sign Up to like & getrecommendations! Published in 2020 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2019.110443
Abstract: Abstract An interfacing system LOCA (ISLOCA) is a bypass accident that results in the release of reactor coolant directly to the outside of a reactor building through a break in part of the low-pressure boundary… read more here.
Keywords: isloca; candu; plant; analysis ... See more keywords
Best-estimate analysis for a MSGTR accident of CANDU-6 plants using the MAAP-ISAAC code
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DOI: 10.1016/j.nucengdes.2019.110452
Abstract: Abstract In CANDU-6 type reactors, a multiple steam generator tube rupture (MSGTR) accident is characterized as a reactor building (RB) bypass scenario. Although the probability of an MSGTR accident in the CANDU-6 type Wolsong plants… read more here.
Keywords: candu; best estimate; accident; estimate analysis ... See more keywords
Calculation of Heat Fluxes Exiting a CANDU Calandria During In-Vessel Retention
Sign Up to like & getrecommendations! Published in 2019 at "Nuclear Technology"
DOI: 10.1080/00295450.2019.1597581
Abstract: Abstract Finite element analysis is used to study heat transfer from a corium pool at the bottom of the calandria to its surroundings during a severe accident in a CANDU 6 reactor. The shape of… read more here.
Keywords: candu; fluxes exiting; heat fluxes; heat ... See more keywords