A Semi-Analytical Method for the Thermal-Hydraulics of a Boiling Water Reactor

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Name thesis:degree_name

M.S. (master's)

Level thesis:degree_level

Thesis

Discipline thesis:degree_discipline

Nuclear, Plasma, and Radiological Engineering

Year dc:date

2017

Author dc:creator

• Vandermyde, Mark A.

• nuclear engineering
• thermal -hydraulics
• boiling water reactor
• neurton flux input
• nodal void fraction
• fuel temperature

Statement dc:rights

• Copyright 1998 Allen John Toreja

Language dc:language

en

Handle dc:identifier

http://hdl.handle.net/2142/96577

OAI identifier oai:identifier

oai:www.ideals.illinois.edu:2142/96577