00898nam0-22003131i-450 99000023621040332120200506105420.088-324-5825-X000023621FED01000023621(Aleph)000023621FED0100002362120020821d1993----km-y0itay50------baitaITy-------001yyArchitettura del paesaggiocriteri di pianificazione e costruzione, con 129 figure e 59 tabelleMario Di Fidio4. ed.MilanoPirola1993XXII, 677 p.25 cmAmbiente e territorioDi Fidio,Mario9602ITUNINARICAUNIMARCBK990000236210403321C 143 CANURB 1935/499DARPUDARPUArchitettura del paesaggio117199UNINA02291nam 2200469 450 991079441660332120210331133021.092-0-133821-X1-5231-4993-01-5231-4994-992-0-133921-6(CKB)4100000011778460(MiAaPQ)EBC6482119(MiAaPQ)EBC30589726(Au-PeEL)EBL30589726(EXLCZ)99410000001177846020210331d2021 uy 0engurcnu||||||||txtrdacontentcrdamediacrrdacarrierCoolant chemistry control and effects on fuel reliability in pressurized heavy water reactors report of a technical meeting /IAEA1st ed.Vienna, Austria :International Atomic Energy Agency,[2021]©20211 online resource (128 pages)IAEA TECDOC Series92-0-134021-4 The focus of this publication is on collecting current practices in Member States related to design extension conditions (DECs) with core melting. The information provided is based on the feedback from technical experts from Canada, France, Finland, India, the Islamic Republic of Iran, the Russian Federation, and the United States of America. There is, however, still no common understanding of DECs due to the complexity of phenomena and insufficient experimental data. This publication identifies current approaches of IAEA Member States with active nuclear power programmes and discusses the regulatory perspective and technical rationale. It attempts to find common practices and possible areas for harmonization of the main rules related to the analysis of DECs with core melting for new water cooled reactors, including their selection for the safety demonstration.IAEA-TECDOC.Pressurized water reactorsPressurized water reactors.621.48336IAEA,MiAaPQMiAaPQMiAaPQBOOK9910794416603321Coolant chemistry control and effects on fuel reliability in pressurized heavy water reactors3739029UNINA