Technical Meeting on the Management of Spent Fuel (Pebbles and Compacts) from High Temperature Reactors

Additional Documents

Postirradiation Examination and Evaluation of Fort St. Vrain Fuel Element 1-0743

by J. J. Saurwein, C. M. Miller, and C. A. Young

General Atomic Project 7400

Published May 1981

Experimental study on the content and distribution of key nuclides in an irradiated graphite sphere of HTR-10

by Hong Li, Xuegang Liu, Feng Xie, Fuming Jia

Nuclear Engineering and Design, Volume 323,

Published August 2017

A comprehensive study on source terms in irradiated graphite spheres of HTR-10

by Feng Xie, Hong Li, Xuegang Liu, Jing Chen, Chuan Li, Xiaotong Chen, Karl Verfondern

Annals of Nuclear Energy, Volume 122,

Published September 2018