1. Boyd, C.F, Hardesty, K., 2003. CFD analysis of 1/7th scale steam generator inlet plenum mixing during a PWR severe accident. U.S. Nuclear Regulatory Commission Report, NUREG-1781.
2. Boyd, C.F, Helton, D.M., Hardesty, K., 2004. CFD analysis of full-scale steam generator inlet plenum mixing during a PWR severe accident. U.S. Nuclear Regulatory Commission Report, NUREG-1788.
3. Level 2 analysis to estimate LERF risk from a thermally induced rupture of a steam generator tube defect;Da Silva;Nuclear Engineering and Design,2008
4. ARTIST: introduction and first results;Guentay;Nuclear Engineering and Design,2004
5. Karwoski, K.J., 2003. U.S. operating experience with thermally-treated Alloy 600 steam generator tubes. U.S. Nuclear Regulatory Commission Report, NUREG-1771.