Heat and Mass Transfer in Reactor Core During a Loca-Single Channel Analysis (Mixed Convection, Numerical, Flow, Thermal-Hydraulics)

Ability to predict the scenario following a loss-of-coolant accident (LOCA) is of central importance in the safety analysis of water reactors. During LOCA, the reactor core is uncovered and the residual water inventory is boiled off by fission products decay heating. For the Three Mile Island (TMI-2) reactor, it was reported that the steam oxidation of Zircaloy reached such an extent that radioactive gases leaked from the interior of the fuel rod and contaminated the primary coolant system. To assess the potential hazard of hydrogen and the concomitant structural damage to fuel cladding, as well as the extent of fission products release, a detailed study of the heat and mass transfer processes during LOCA was made.

Name thesis:degree_name

Ph.D.

Level thesis:degree_level

Dissertation

Discipline thesis:degree_discipline

Mechanical Engineering

Grantor

University of Illinois at Urbana-Champaign

Year dc:date

2014

Author dc:creator

• Pien, Shyh-Jye

• Engineering, Mechanical

Identifier

(UMI)AAI8600284

OAI identifier oai:identifier

oai:www.ideals.illinois.edu:2142/70134