A Computation Thermal-Hydraulics Analysis of a Heragonal-Geometry 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

• Laughton, Terrill R.

• nuclear engineering
• thermal-hydraulics
• hexagonal geometry reactor
• computational nodal methods code
• steady state thermal-hydraullics parameters
• neutronics code
• neutron flux
• macrocsopic fission cross sections

Statement dc:rights

• Copyright 1997 Erik Stefan Kirstein

Language dc:language

en

Handle dc:identifier

http://hdl.handle.net/2142/96428

OAI identifier oai:identifier

oai:www.ideals.illinois.edu:2142/96428