1. A. H. Booth, “A Method of Calculating Fission Gas Release from UO2 Fuel and Its Implication to the X-2-f Loop Test,” Atomic Energy of Canada Limited Report - 496, 1957.
2. CEGA, “NP-MHTGR Material Models of Pyrocarbon and Pyrolytic Silicon Carbide,” CEGA Corporation, CEGA-002820, Rev. 1, 1993.
3. Two-decade DOE investment lays foundation for TRISO fueled reactors in the US;Demkowicz;Nuclear News,2020
4. “Final Report – NGNP Core Performance Analysis, Phase 2,” Report 911184, Rev. 0, General Atomics, 2009.
5. Fuel Performance and Fission Product Behaviour in Gas Cooled Reactors;IAEA;TECDOC-9787,1997