Fuel R&D at Studsvik II. General studies of fuel behaviour including pellet-cladding interaction (original) (raw)

Simulation with DIONISIO 1.0 of thermal and mechanical pellet-cladding interaction in nuclear fuel rods

Alicia Denis

Journal of Nuclear Materials, 2008

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Analysis of pellet-clad interaction of LWR fuel rods during power ramps

A. R. Massih

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The mechanical behaviour of fast reactor fuel

Juan Matthews

1971

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Handling, Transport and Program for Post-Irradiation Examination of Special Fuel Rods

Sten Lundberg

2018

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Simulation of Mechanical Behavior of Fuel Pellets With Different Geometries

Paulo A Rodi

Brazilian Journal of Radiation Sciences, 2019

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Using Finite Model Analysis and Out of Hot Cell Surrogate Rod Testing to Analyze High Burnup Used Nuclear Fuel Mechanical Properties

Jy-An Wang

2014

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The Performance of High-Temperature Reactor Fuel Particles at Extreme Temperatures

Heinz Nabielek

Nuclear Technology, 1989

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Experiment Assembly and Testing in Hot Cell in Support of Advanced Fuels Irradiation Testing

Justin Yarrington

U.S. Department of Energy Office of Scientific and Technical Information - OSTI OAI, 2022

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Properties of the high burnup structure in nuclear light water reactor fuel

Thierry Wiss

Radiochimica Acta

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Burnup characteristic of CERMET and TRISO fuel particles used in Boiling Water Reactor with Pebble-Bed Coated Particles

Abdelfettah Benchrif, Abdelouahed Chetaine

SOP Transactions on Theoretical Physics, 2014

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Modelling of Pellet-Clad Interaction During Power Ramps

A. R. Massih

2004

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A study into the dependence of the cladding-fuel pellet gap conductance on burn-up and the effects on the reactor core neutronic performance

rashdan malkawi

Nuclear Energy and Technology

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FETMA: A Simple Code for Thermo-Mechanical Analysis on BWR Fuel Rods

Co. SEP

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ThermoMechanical Analysis of Coated Particle Fuel Experiencing a Fast Control Rod Ejection Transient

Javier Ortensi

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Post-Irradiation Examinations of High-Burnup PWR Fuel Rods – Initial Results

Bruce Bevard

2018

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3D Simulation of Missing Pellet Surface Defects in Light Water Reactor Fuel Rods

Jason Hales

2012

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Development of New Reactor Fuel Materials

Hadi Suwarno

Journal of Nuclear Science and Technology, 1995

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Stress Analysis of Coated Particle Fuel in the Deep-Burn Pebble Bed Reactor Design

Abderrafi Ougouag

2010

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Investigation of the release of gaseous fission products from pebble bed molecular reactor's triso coated fuel particle during the HFR-K5 fuel irradiation test

Mosebetsi Leotlela

2010

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Fuel behavior comparison for a research reactor

Mirea Mladin

Journal of Nuclear Materials, 2006

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An approach for evaluating the integrity of fuel applied in Innovative Nuclear Energy Systems

Hiroshi Sekimoto

2014

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Thermal analysis of ceramic nuclear fuels for the HPLWR

Genrry Delgado

Annals of Nuclear Energy, 2019

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Design of a fuel element for a lead-cooled fast reactor

Malambu Mbala

Journal of Nuclear Materials, 2009

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Effects of %FIMA on Storage-Safety Parameters of Spent Fuel from Experimental Pebble-Bed Reactor

aisyah aisyah

2021

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Session 2 Fuel development, qualification, fabrication and licensing

G. Hofman

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Severe Fuel Damage Experiments With Advanced Cladding Materials to be Performed in the QUENCH Facility (QUENCH-ACM)

Juri Stuckert

Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 2008

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Non-destructive Evaluation of Irradiated Nuclear Fuels and Structural Components from Indian Reactors

Nitin Kumawat

2017

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Investigation of the performance parameters and temperature distribution in fuel rod dependent on operation periods and first wall loads in fusion–fission reactor system fueled with ThO2

Osman Ipek

Energy Conversion and Management, 2003

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A REVIEW OF FAILURE MODES OF NUCLEAR FUEL CLADDING A Review of Failure Modes of Nuclear Fuel Cladding

Abdoulhadi A . Borhana Omran

Journal of Engineering Science and Technology, 2019

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Fast Reactor Fuel Pin Behaviour Modelling in the Uk

Juan Matthews

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Modeling and simulation of coupled nuclear heat energy deposition and transfer in the fuel assembly of the Ghana Research Reactor-1 (GHARR-1)

Felix Ameyaw

Nuclear Engineering and Design, 2011

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Benchmark results for the “BWR-PB” fuel assembly based on pebble-bed coated particles with uranium dioxide and gadolinia poison

Abdelfettah Benchrif, Abdelouahed Chetaine

2009

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An approach for evaluating fuel system applied in innovative nuclear energy system

Hiroshi Sekimoto

Progress in Nuclear Energy

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Results of AVR fuel pebble irradiation at increased temperature and burn-up in the HFR Petten

Daniel Freis

Nuclear Engineering and Design, 2008

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