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

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Έτος:

1993

Γλώσσα:

english

Σελίδες:

227

Αρχείο:

PDF, 15.18 MB

IPFS:

,

english, 1993

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Ίσως σας ενδιαφέρει

— Control Assembly Materials for Water Reactors (IAEA TECDOC-1132)

— Fuel Modelling at Extended Burnup (IAEA TECDOC-998)

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

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

— Fuels (nuclear) Development Operations [Jul-Sep 1959] [Declassified]

— 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 2 (csni-r2003-8-vol2)

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

— System 80+ Standard [nucl. powerplnt] Design - Vol 04

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

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

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

— Zircalloy Clad [nuclear] Fuel Analysis

Olsen, C.S.; Sterbentz, J.W.; Sinha, U.P.; USDOE, Washington, DC (United States);National Academy of Sciences, Washington, DC (United States); Idaho National Engineering Laboratory.; Idaho National Engineering and Environmental Laboratory.; United States. — Weapons-grade plutonium dispositioning. Volume 4. Plutonium dispositioning in light water reactors

International Atomic Energy Agency — Development status of metallic, dispersion and non-oxide advanced and alternative fuels for power and research reactors

William L R Rice; U.S. Atomic Energy Commission. Division of Reactor Development — Nuclear fuels and materials development

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

— Research Reactor Fuel Management 1 (RRFM 1997)

— Research Reactor Fuel Management 4 (RRFM 2000)

— Research Reactor Fuel Management 7 (RRFM 2003)

OECD — Nuclear fuel safety criteria technical review

coll. — State-of-the-Art Report on Light Water Reactor Accident-Tolerant Fuels

Brian R. T. Frost (Auth.) — Nuclear Fuel Elements. Design, Fabrication and Performance

A. M. Judd (Auth.) — Fast Breeder Reactors. An Engineering Introduction

Alan Edward Waltar, Albert Barnett Reynolds — Fast Breeder Reactors

R.J.M. Konings (editor) — Comprehensive Nuclear Materials, Volume 2: Material Properties / Oxide Fuels for Light Water Reactors and Fast Neutron Reactors

Markus H.A. Piro (editor) — Advances in Nuclear Fuel Chemistry (Woodhead Publishing Series in Energy)

H. Matzke and G. Schumacher (Eds.) — Nuclear Materials for Fission Reactors

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