Proceedings of Topical Meeting on RIA Vol 2...

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Proceedings of Topical Meeting on RIA...

Proceedings of Topical Meeting on RIA Vol 2 (csni-r2003-8-vol2)

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Rok:

2003

Język:

english

Strony:

147

Plik:

PDF, 10.74 MB

IPFS:

,

english, 2003

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— Long-Term Storage of Spent Nuclear Fuel (IAEA TECDOC-1293)

— Studies on Fuels with Low Fission Gas Release (IAEA TECDOC-970)

— Adv Fuel Pellet Mtls, Designs for Water-Cooled Reactors (IAEA TECDOC-1416)

— Adv in Fuel-Pellet Tech for Imprvd Perf at High Burnup (IAEA TECDOC-1036)

— Advanced Post-Irradiation Exam Tech for Water-Reactor Fuel (IAEA TECDOC-1277)

— Behavior of a Fuel Bundle Simularor During Heatup, Flooding (csni85-98)

— Behavior of LWR Core Materials Under Accident Conditions (IAEA TECDOC-921)

— Fission Gas Release, Fuel Rod Chem Related to Extended Burnup (IAEA TECDOC-697)

— Fuel Safety Criteria - Tech Review (csni-r99-25)

— Fuels [nuclear] Development Operation [qtrly rpt, Apr-Jun 1961] [declassified]

— Fuels [nuclear] Development Operation [qtrly rpt, Jan-Mar 1961] [declassified]

— In-Vessel Core Degradation [validation martrix] (csni-r2000-21)

— Nuclear Fuel Behavior Modelling at High Burnup (and exper support) (IAEA TECDOC-1233)

— Proceedings of Topical Meeting on RIA Vol 1 (csni-r2003-8-vol1)

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

— Status of Degraded Core Issues (csni-r2001-5)

— Thermo-Hydraulic Codes for VVER LOCA and Transients (csni-r2001-4)

— Transient Behavior of High-Burnup Fuel (csni-r1996-23)

— Transient Behavior of High-Burnup Fuel (csni-r95-22)

— VVER-Specific Features [core degradation] (csni-r98-20)

— Water Channel Reactor Fuels, Fuel Channels [des, perf] (IAEA TECDOC-997)

— Water Reactor Fuel Element Modeling at High Burnup (IAEA TECDOC-0957)

— Water Reactor Safety Info Meeting Vol 2 [22nd, transactions]

— Zircalloy Clad [nuclear] Fuel Analysis

International Atomic Energy Agency — Fuel failure in normal operation of water reactors : experience, mechanisms and management : proceedings of a Technical Committee meeting held in Dimitrovgrad, Russian Federation, 26-29 May 1992

Manfred Firnhaber; Gesellschaft für Reaktorsicherheit (Köln) — CORA-13 experiment on severe fuel damage : comparison report

T J Haste; K Trambauer; OECD Nuclear Energy Agency. Committee on the Safety of Nuclear Installations — Degraded core quench : summary of progress, 1996-1999 : executive summary

Nuclear Energy Agency Committee on the Safety of Nuclear Installations — In-vessel core degradation code validation matrix

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International Atomic Energy Agency. Technical Committee on Recycling of Plutonium and Uranium in Water Reactor Fuel — Recycling of plutonium and uranium in water reactor fuel : proceedings of a Technical Committee meeting held in Newby Bridge, Windermere, United Kingdom, 3-7 July 1995

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