Ebook: Review of nuclear fuel experimental data : fuel behaviour data available from IFE-OCDE Halden Project for development and validation of computer codes

Today it is no longer possible to support nuclear power operation without computer code calculations which treat all aspects of fuel performance simultaneously and consistently. The need for calculations to represent best estimates requires that computer codes be developed and validataed against good quality data. The best quality data for this purpose come from well-instrumented and dedicated test reactors. This report reviews the data available from the OECD Halden Reactor Project and touches upon that available from other sources. It concentrates on experiments on thermal performance, fission product release, clad properties, and pellet-clad interaction. It also discusses the creation of an internationally available database covering as many reactor systems as possible, and related issues