Computer Render of the OSTR with 4 beamports, the thermal column, the bioshield, and the core itself
College of Engineering Unit: 
Nuclear Science and Engineering
Project Team Member(s): 
Maxwell Kavanagh - kavanagm@oregonstate.edu
Benjamin Dibley - dibleyb@oregonstate.edu
Cooper Anderson - andercoo@oregonstate.edu
Project ID: 
NSE.9
Project Description: 

The Oregon State University TRIGA Reactor (OSTR) is primarily used as a research tool for materials to be irradiated with neutrons or gamma rays. The OSTR currently operates at a maximum steady state power of 1.1MW. This operating power has been approved by the Nuclear Regulatory Commission (NRC) through a rigorous Safety Analysis Report (SAR). Currently there are plans to increase the power of the OSTR, which will allow for greater research capabilities. An increase in power of the OSTR must be approved by the NRC, and a new SAR will have to be completed, which includes a section on accident analysis. One important accident to analyze is a loss of coolant accident (LOCA). This project uses an updated methodology, using computer simulations to show that in a LOCA event, the dose to workers and the public are under the federal regulations for a non-power reactor with an increased power level.

Opportunities: 
This team is open to networking
This team is open to employment offers
Team Captain/Coordinator Email Address: