1. Measurement and analysis of fission gas release from BNFL's SBR MOX fuel
2. Geelhood KJ, Luscher WG, Raynaud PA, et al. FRAPCON-4.0: a computer code for the calculation of steady-state, thermal-mechanical behavior of oxide fuel rods for high burnup. US: Pacific Northwest National Laboratory; 2015. (PNNL-19417).
3. Porter IE, Geelhood KJ, Colameco DV, et al. FAST-1.0: a computer code for thermal-mechanical nuclear fuel analysis under steady-state and transients. US: Pacific Northwest National Laboratory; 2020. (PNNL-29720).
4. Lassmann K, Schubert A, Van Uffelen P, et al. Transuranus Handbook version “v1m1j06”. EU: European Commission, Joint Research Center, Institute for Transuranium Elements; 2006.