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Fuel Modelling in Accident Conditions (FUMAC)

Final Report of a Coordinated Research Project

English IAEA-TECDOC-1889 978-92-0-163919-6
180 175 18.00 2019

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This publication summarizes the findings and conclusions of an IAEA coordinated research project (CRP) on fuel modelling in accident conditions, which was initiated under the IAEA Action Plan on Nuclear Safety following the Fukushima accident. The overall aim of the project was to analyse and better understand fuel behavior in accident conditions, with a focus on loss of coolant accidents. In the course of the project the participants used a mixture of data derived from accident simulation experiments, in particular data designed to investigate the fuel behaviour during design basis accident and design extension conditions. They carried out calculations on priority cases selected from a matrix of cases identified at the first research coordination meeting and designed to support their individual priorities. These priority cases were chosen as the best available to help determine which of the many models used in the codes best reflect reality. The CRP provided an ideal platform to compare their code results with others and especially with experimental data, to which they otherwise would not have had access. The achievements made within this CRP fostered new collaborations and enhanced the development and improvement of common models and highlighted differences in the interpretation of some experiments and therefore in the use of the codes ? the so-called user effects.

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FUMAC, Fuel Modelling in Accident Conditions, Fuel Modelling, Accident Conditions, Fuel Performance, Fuel Management, Fuel Behaviour, Fukushima Daiichi, NPP, Nuclear Power Plant, Separate Effect Test, Halden Loca Test, Studsvik Loca Test, Model Improvements, Single Fuel Rod Codes, Coupled Thermal Hydraulic and Fuel Rod Codes, Accident Codes, Methodology, MTA EK Burst Test

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