Numerical Modelling of the No-Core-Melt Passive Safety Feature in the Generation IV Canadian SCWR

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Creator: 

Schmidt, Graeme

Date: 

2014

Abstract: 

Heat transfer through a typical fuel channel in a Generation IV Canadian Supercritical Water Reactor was modelled numerically using Finite Element Method software. With the objective of limiting the fuel cladding to sub-melting temperatures during a Loss of Coolant Accident, it was found that two distinct fuel channel designs both attained maximum cladding surface temperatures of T = 1,120 C; a result that compared favourably with the 1,450 C melting point of the stainless steel cladding. However, given the similar temperatures yielded by the reference and alternate fuel channel designs, it
was deemed necessary to devise another metric for identifying the better performing variant. In this vein, the ratios of LOCA to normal operation thermal fluxes were computed and it was observed that the reference configuration performed best by limiting losses in normal operation while also permitting sufficient heat rejection to the moderator during the LOCA.

Subject: 

Engineering - Aerospace

Language: 

English

Publisher: 

Carleton University

Thesis Degree Name: 

Master of Applied Science: 
M.App.Sc.

Thesis Degree Level: 

Master's

Thesis Degree Discipline: 

Engineering, Aerospace

Parent Collection: 

Theses and Dissertations

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