A DESIGN CORRELATION FOR PRESSURE DROPS IN COILED, ONCE-THROUGH STEAM GENERATORS.CAMPOLUNGHI F; CUMO M; FERRARI C et al.1976; TERMOTECNICA; ITAL.; DA. 1976; VOL. 30; NO 12; PP. 662-670; ABS. ITAL.; BIBL. 6 REF.Article

Accident loads for a VVER-440/213 containmentTECHY, Z; LAJTHA, G; TAUBNER, R et al.Nuclear engineering and design. 1995, Vol 157, Num 3, pp 375-385, issn 0029-5493Article

Assessment of reactor vessel integrity (ARVI)SEHGAL, B. R; KARBOJIAN, A; TECHY, Z et al.Nuclear engineering and design. 2005, Vol 235, Num 2-4, pp 213-232, issn 0029-5493, 20 p.Conference Paper