Thermal transport of oxide and nitride nuclear fuels after irradiation

When and Where

Apr 11, 2025
10:45am - 11:00am

Summit, Level 3, Room 348

Presenter(s)

Zilong Hua

Amey Khanolkar

Ella Pek

Saqeeb Adnan

Kaustubh Bawane

Anshul Kamboj

J. Matthew Mann

Jennifer Watkins

Marat Khafizov

David Hurley

Co-Author(s)

Zilong Hua¹,Amey Khanolkar¹,Ella Pek¹,Saqeeb Adnan²,Kaustubh Bawane¹,Anshul Kamboj¹,J. Matthew Mann³,Jennifer Watkins¹,Marat Khafizov²,David Hurley¹

Idaho National Laboratory¹,The Ohio State University²,Air Force Research Laboratory³

Abstract

Zilong Hua¹,Amey Khanolkar¹,Ella Pek¹,Saqeeb Adnan²,Kaustubh Bawane¹,Anshul Kamboj¹,J. Matthew Mann³,Jennifer Watkins¹,Marat Khafizov²,David Hurley¹

Idaho National Laboratory¹,The Ohio State University²,Air Force Research Laboratory³

Nuclear fuel thermal conductivity directly impacts reactor safety and efficiency. This presentation summarizes our recent investigation at Idaho National Laboratory on thermal transport behavior of actinide materials ThO2, UO2, U-ThO2, and UN in pristine and irradiated states. Through a comprehensive analysis of phonon scattering mechanisms, we investigate the defect generation and evolution within fuels throughout their service life, and the corresponding impacts on their thermal conductivity.

Keywords

thermal conductivity

Symposium Organizers

Yee Kan Koh, National University of Singapore

Zhiting Tian, Cornell University

Tianli Feng, University of Utah

Hyejin Jang, Seoul National University

Session Chairs

Yee Kan Koh