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Massachusetts Institute of Technology

Design and Modeling of Offshore Nuclear Platform Fuel and Transfer System

Abstract

dc:description.abstract

The design and modeling of the fuel and transfer system aboard the Offshore Nuclear Platform (OFNP) aims to integrate Small Modular Reactors (SMRs) into an offshore setting. This endeavor is in line with global initiatives to mitigate temperature rise by 2050, using nuclear energy for electrical generation “Key Aspects of the Paris Agreement | UNFCCC.” A specific focus on high-temperature gas reactors, notably pebble bed reactors for their compact fuel form and capability for at-power fuel replenishment through TRISO fuel pebbles recirculation will be evaluated. This study will review both historical and current high-temperature gas reactors, focusing on their development, application, and operational efficiencies. Special emphasis will be placed on methods for managing spent fuel, including storage and environmental considerations. The research will develop the platform’s conceptual fuel transfer system which details the design of fuel storage, handling and at sea transfer system, ensuring safety, particularly during at-sea offloading operations. Additionally, the thesis will assess the platform's stability, transfer system structural integrity, and shielding design to determine its feasibility for offshore energy generation for the reactor’s lifetime.

Degree

thesis:*
Name thesis:degree_name
Master
Department dc:contributor.department
Massachusetts Institute of Technology. Department of Mechanical Engineering
Grantor dc:publisher
Massachusetts Institute of Technology
Year dc:date.issued
2024

Author and committee

dc:creator, dc:contributor.*
Author dc:creator
  • Allison, Asia
Advisor dc:contributor.advisor
  • Golay, Michael

Rights

dc:rights
Statement dc:rights
  • In Copyright - Educational Use Permitted
  • Copyright retained by author(s)

Identifiers

dc:identifier.*
Handle dc:identifier.uri
https://hdl.handle.net/1721.1/155854
OAI identifier oai:identifier
oai:dspace.mit.edu:1721.1/155854

Chain of custody

source
Harvested from
MIT
Base URL
dspace.mit.edu/oai/request
Last updated
2026-07-22
Source record
OAI-PMH GetRecord
related terms
citation

Allison, Asia. Design and Modeling of Offshore Nuclear Platform Fuel and Transfer System. Massachusetts Institute of Technology, 2024. https://hdl.handle.net/1721.1/155854