Materials management strategies for VVER reactors - Materials' Ageing and Degradation in Light Water Reactors - page 318

Katona , T. et al . (2009b). Extension of Operational Life-Time of VVER-440/213
Type Units at Paks Nuclear Power Plant. In: Proceedings of the ASME
Pressure Vessels and Piping Conference. ASME 2009: Sustainable Energy
for the Third Millennium, Prague, Czech Republic 2009.07.26-2009.07.30.
American Society of Mechanical Engineers, p. CD-ROM. Paper PVP2009-
77911 (ISBN:9780791838549).
Katona , T. et al . ( 2010 ). Time-limited Ageing Analyses for Justifi cation of Long-Term
Operation of Paks NPP. In: ASME International Mechanical Engineering
Congress and Exposition. Vancouver Canada 2010.11.12-2010.11.18. Paper
IMECE2010-40201 (ISBN:978-0-7918-3891-4).
Katona , T. and Bajsz , J. ( 1992 ). Plex at Paks - making a virtue out of necessity. Nuclear
Engineering International 37 (455) pp. 27-31.
Katona , T. and R á tkai , S. ( 2008 ). Extension of operational life-time of VVER-440/213
type units at Paks nuclear power plant. Nuclear Engineering and Technology
40(4) pp. 269-76.
Katona , T. and R á tkai , S. ( 2010 ). Programme of Long-term Operation of Paks
Nuclear Power Plant. In: Transactions of ENC 2010: European Nuclear
Conference 2010, Barcelona, Spain 2010.05.30-2010.06.02. Paper A0114
(ISBN:978-92-95064-09-6).
Katona , T. , R á tkai , S. and Pammer , Z. ( 2007 ). Reconstitution of Time-limited
Ageing Analyses for Justifi cation of Long-Term Operation of Paks NPP. In:
19th International Conference on Structural Mechanics in Reactor Technology
(SMiRT 19). Toronto, Canada, 2007.08.12. Paper D02/2-1.
Katona , T. , R á tkai , S. and Pammer , Z. ( 2011 ). Reconstitution of time-limited age-
ing analyses for justifi cation of long-term operation of Paks NPP. Nuclear
Engineering and Design Volume 241 Issue 3 (March 2011) pp. 638-43.
Katona , T. et al . (2005). Key Elements of the Ageing Management of the
VVER-440/213 type Nuclear Power Plants. In: 18th International Conference
on Structural Mechanics in Reactor Technology (SMiRT 18). Beijing, China
2005.08.07-2005.08.12. Paper D02-4.
Kupca , L. ( 2006 ). Irradiation Embrittlement Monitoring Programs of RPV ' s in
the Slovak Republic NPP's. In: 14th International Conference on Nuclear
Engineering (ICONE 14), Miami FL (United States) 17-20 July 2006.
NPO Hidropress ( 2007 ). Steam Generator PGV-213. Analysis of Material Properties
of Steam Generator Tubes (In Russian). NPO Hidropress Report No. U213D3
2007.
Orgenergostroy ( 1989a ). Instruction of technical servicing for standardized units
VVER-1000 NPP type B-320 containment pre-stressed system, Moscow, 1989.
Orgenergostroy ( 1989b ). Instruction of technical servicing for main series
(non-standardized) units VVER-1000 NPP type 302338 and 187 containment
pre-stressed system, Moscow, Orgenergostroy, 1989.
Popov, V. (2007). The large projects at Kozloduy NPP - with focus on long time oper-
ation and ageing management, Second IAEA International Symposium on
Nuclear Power Plant Life Management, 15-18 October 2007 Shanghai China.
Rosenergoatom ( 2003 ). Safety enhancement and lifetime extension of the power
unit 1 of Kola NPP, Summary Report, Moscow, 2003.
Slovak Report ( 2010 ). National Report of the Slovak Republic Compiled in Terms
of the Convention on Nuclear Safety June 2010 http://www.ujd.gov.sk/fi les/
dokumenty/NS_NS_2010.pdf .

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