The goals of this project were to analyze the fast neutron flux coming through the surface of the solid state heatpipe eVinci Micro Reactor to better understand its research capabilities and to design shielding for the neutrons. To achieve these goals the Monte Carlo N-Particle transport code was utilized for determining neutron flux and appropriate sizing for the nuclear reactor core and shielding. Appropriate dimensions of the reactor core for adequate neutron surface flux was found and shielding materials and size was made for safety.

• This report represents the work of one or more WPI undergraduate students submitted to the faculty as evidence of completion of a degree requirement. WPI routinely publishes these reports on its website without editorial or peer review.

Creator

• Flanagan, Seamus

Publisher

• Worcester Polytechnic Institute

Identifier

• 65641
• E-project-042822-150414

Parola chiave

• Fast Neutron Analysis
• Micro Reactor
• MCNP
• Nuclear

Advisor

• Sisson, Richard D.
• Medich, David Christopher

Year

• 2022

Date created

• 2022-04-28

Resource type

• Major Qualifying Project

Major

• Mechanical Engineering

Rights statement

• In Copyright