1. Consolidation of scientific and technological expertise to assess the reliability of reactor pressure vessel embrittlement prediction in particular for the arctic area plant (COBRA);Ballesteros;Nuclear Engineering and Design,2005
2. Ballesteros, A., Jardí, X., Böhmer, B., Konheiser, J., Ošmera, B., Kyncl, J., Keresztúri, A., Hordosy, G., Ilieva, K., Belousov, S., Kirilova, D., Mitev, M., Petrov, B., Acosta, B., Smutný, V., Polke, E., Zaritsky, S., Töre, C., Ortego, P., 2005. Reactor Dosimetry: Accurate Determination and Benchmarking of Radiation Field Parameters, Relevant for Pressure Vessel Monitoring (REDOS). AMES Report No. 17, EUR 21771 EN. Available from: http://safelife.jrc.nl/ames/publications/index.php.
3. Sensitivity analysis and neutron fluence adjustment for VVER-440 RPV;Belousov;Journal of ASTM International,2006
4. Sensitivity analysis and neutron fluence adjustment for RPV VVER-1000;Belousov,2003
5. MCNP – a General Monte Carlo N-Particle Transport Code, Version 4C,2000