An Analysis of the Thermal-Hydraulic Behavior of an Open Lattice Core at System Pressures of 1750 and 2250 PSIA

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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

• Jordan, Robert P.

• nuclear engineering
• thermal-hydraulic parameters
• open lattice core
• system pressures
• spatial nodal network
• phenomenological modeling

Statement dc:rights

• Copyright 2007 Li Ji

Language dc:language

en

Handle dc:identifier

http://hdl.handle.net/2142/96398

OAI identifier oai:identifier

oai:www.ideals.illinois.edu:2142/96398