Coolant Tech. of Water-Cooled Reactors Vol 2 [Corrosion in...

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Coolant Tech. of Water-Cooled Reactors Vol 2 [Corrosion in Pri Coolant Sys] (IAEA TECDOC-667v2)

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ఈ పుస్తకం ఎంతగా నచ్చింది?

దింపుకొన్న ఫైల్ నాణ్యత ఏమిటి?

పుస్తక నాణ్యత అంచనా వేయడాలనుకుంటే దీన్ని దింపుకోండి

దింపుకొన్న ఫైళ్ళ నాణ్యత ఏమిటి?

సంవత్సరం:

1992

భాష:

english

పేజీల సంఖ్య:

72

ఫైల్:

PDF, 5.16 MB

IPFS:

,

english, 1992

ఆన్‌లైన్‌లో చదవండి

దింపుకోలు (pdf, 5.16 MB)

కి మార్పిడి జరుగుతూ ఉంది.

కి మార్పిడి విఫలమైంది!

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— Coolant Tech. of Water-Cooled Reactors Vol 1 [Chemistry of Pri Coolant] (IAEA TECDOC-667v1)

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— Corrosion of Zr Alloys in Nuclear Powerplants (IAEA TECDOC-684)

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— Ageing of Nucl. Powerplant Compnts. - BWR Pressure Vessel Internals (IAEA TECDOC-1471)

— Durability of Spent Nucl Fuels, Facility Components in Wet Storage (IAEA TECDOC-1012)

— Erosion and Corrosion of Nuclear Powerplant Mtls (csni-r1994-26)

— Flow Locallization Procs in Deformation of Irradiated Reactor Structure Alloys

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— Fusion Reactor Materials [Semi-Annual Rpt Mar 31, 1993]

— Infl of High-Dose Irrad on Core Struct, Fuel Mtls - Adv Reactors (IAEA TECDOC-1039)

— Metallurgy Research - Quarterly Prog Rpt [Jan-Mar 1956] [Declassified]

— Mgmt of Ageing of PWR Vessel Internals (IAEA TECDOC-1119)

— Novel Concepts for Damage-Resistant Alloys in Next-Gen Nuclear Powerplants

— Reactor and Materials Tech Monthly Rpt [May, 1965] [Declassified]

— Scientific Issues in (nuclear) Fuel Behavior (NEA 0213)

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Davis, Joyce S.; Harries, D. R — Irradiation embrittlement and creep in fuel cladding and core compounds : proceedings of the Conference organized by the British Nuclear Energy Society in London, 9-10 November 1972

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