Pellet-clad interaction in water reactor fuels [electronic resource] : seminar proceedings, Aix-en-Provence, France, 9-11 March 2004 / hosted by CEA Cadarache, DEN, DEC ; in co-operation with EDF ... [et al.].

Show other versions (1)

Bibliographic Details
Corporate Authors:	Commissariat à l'énergie atomique, Cadarache Direction de l'énergie nucléaire DEC Electricité de France OECD Nuclear Energy Agency
Language:	English
Published:	Paris : Nuclear Energy Agency, Organisation for Economic Co-operation and Development, c2005.
Subjects:	Nuclear fuel claddings > Congresses. Light water reactors > Congresses.
Genre:	Congresses.
Online Access:	OECD-iLibrary Books, Papers & Statistics: 2005 (Digital Object Identifier Permalink)
Variant Title:	Pellet-clad Interaction in Water Reactor Fuels: Seminar Proceedings, Aix-en-Provence, France, 9-11 March 2004
Format:	Electronic eBook

Similar Items

Pellet-clad interaction in water reactor fuels : seminar proceedings, Aix-en-Provence, France, 9-11 March 2004
Published: (2005)

Properties of light water reactor spent fuel cladding
by: Farwick, D. G.
Published: (1979)

Variations in zircaloy-4 cladding deformation in replicate LOCA simulation tests
by: Longest, A. W.
Published: (1982)

Pellet-cladding mechanical interaction in Halden assembly IFA-226
by: Owen, Dennis E.
Published: (1978)

An assessment of fuel melting, radial extrusion, and cladding thermal failure during a power-cooling-mismatch event in light water reactors
by: El-Genk, Mohamed S.
Published: (1979)

Calibration of a fuel-to-cladding gap conductance model for fast reactor fuel pins
by: Baker, R. B.
Published: (1978)

SIFAIL, a subprogram to calculate cladding deformation and damage for fast reactor fuel pins
by: Wilson, D. R. (Donald Randall), 1936-
Published: (1979)

Oxidation and embrittlement of zircaloy-4 cladding from high temperature film boiling operation
by: Seiffert, Stephen L.
Published: (1979)

Light water reactor fuel rod modeling code evaluation. Phase 1, Topical report.
Published: (1975)

Light water reactor fuel rod modeling code evaluation. Phase II, Topical report.
Published: (1976)

Predicted increase in fuel rod cladding oxidation.
Published: (1998)

Modeling of crack growth in oxidized zircaloy cladding during thermal-shock conditions
by: Majumdar, S. (Saurindranath)
Published: (1978)

Evaluation of simulated-LOCA tests that produced large fuel cladding ballooning
by: Powers, D. A. (Dale A.)
Published: (1979)

In-pile observation of fuel and clad relocation during LMFBR core-disruptive accidents
by: Wright, S. A.
Published: (1989)

ECCS calculations on fuel cladding.
Published: (1979)

Measured in-reactor data and postirradiation observations for IFA-527
by: Cunningham, M. E.
Published: (1984)

Creepdown of zircaloy fuel cladding-initial tests
by: Hobson, D. O.
Published: (1978)

Results from the run-beyond-cladding-breach irradiation of a predefected fuel pin (RBCB-6)
by: Langstaff, D. C.
Published: (1979)

Results from the run-beyond-cladding-breach irradiation of a predefected fuel pin (RBCB-7)
by: Langstaff, D. C.
Published: (1980)

Light-water-reactor safety fuel systems research programs : quarterly progress report
Published: (1985)

The Analysis of fuel relocation for the NRC/PNL Halden assemblies IFA-431, IFA-432, and IFA-513
Published: (1980)

Cladding swelling and rupture models for LOCA analysis
by: Powers, D. A. (Dale A.)
Published: (1980)

Light water reactor nuclear fuel cycle
Published: (1981)

Cladding rupture, swelling & coolant blockage as a result of a reactor accident.
Published: (1979)

An aluminum-zircaloy galvanic couple in reactor water
by: Horton, Ralph M.
Published: (1978)

Effect of particle blending on HTGR fuel rod temperature profiles : HTGR fuel recycle development program (189a OHO45) Fuel Refabrication, task 500
by: Angelini, P., 1932-
Published: (1979)

Detection of small-sized near-surface under-clad cracks for reactor pressure vessels
Published: (1983)

Results from irradiation of vented GCFR fuel rods in the GB-9 and GB-10 capsule experiments
by: Longest, A. W.
Published: (1978)

Control rod guide tube wear in operating reactors : operating experience report.
by: Riggs, R.
Published: (1980)

Inventory and characterization of spent LWR fuel
by: Funk, C. W.
Published: (1979)

Biaxial creep behavior of ribbed GCFR cladding at 650.
Published: (1977)

Data base on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂?fuel (VVER type) under reactivity accident conditions.
by: Yegorova, L. A. (Larisa Alexandrovna)
Published: (1999)

Proceedings of the Technical Seminar on the Treatment, Conditioning, and Storage of Solid Alpha-Bearing Waste and Cladding Hulls, Paris, 5th-7th December 1977 = Compte rendu du Séminaire technique sur le traitement, le conditionnement et le stockage des déchets solides alpha et des coques de dégainage, Paris, 5-7 décembre 1977
Published: (1978)

Deformation characteristics of Zircaloy cladding in vacuum and steam under transient-heating conditions : summary report
by: Chung, H. M.
Published: (1978)

Power burst facility thermocouple effects test results report, test series TC-1, TC-3, and TC-4
by: Garner, Richard W.
Published: (1982)

Effects of environments on spent fuel
by: Funk, C. W.
Published: (1979)

Accident-tolerant materials for light water reactor fuels
by: Rebak, Raúl B. (Raul Basilio), 1956-
Published: (2020)

NUREG-0630 "Cladding, swelling and rupture--models for LOCA analysis".
Published: (1980)

Report on ECCS cladding models, NUREG-0630.
Published: (1980)

Experiment operations plan for the MT-3 experiment in the NRU reactor
Published: (1983)