1. Shoji T: ‘Progress in the mechanistic understanding of BWR SCC and its implication to the prediction of SCC growth behavior in plants’, Proc. 11th Int. Conf. on ‘Environmental degradation materials nuclear power systems-water reactors’, Stevenson, WA, USA, August 2003, ANS, 588–598.
2. Ehrnstén U, Hänninen H, Aaltonen P, Jansson C, Nenonen P and Angeliu T: ‘Intergranular cracking of AISI 316NG stainless steel in BWR environment’, Proc. 10th Int. Conf. on ‘Environmental degradation materials nuclear power systems-water reactors’, Lake Tahoe, CA, USA, August 2001, NACE, CD ROM.
3. Angeliu TM, Andresen PL, Hall E, Sutliff JA, Sitzman S and Horn RM: ‘Intergranular stress corrosion cracking of unsensitized stainless steels in BWR environments’, Proc. 9th Int. Conf. on ‘Environmental degradation materials nuclear systems-water reactors’, Newport Beach, CA, USA, August 1999, TMS, 311–317.