The status of the different studies, completed or currently being carried out by the expert group are summarised in the following table. When a benchmark is completed, a link is made to the list of publications. When a benchmark is ongoing, a link is provided to the specifications.
| Benchmark | Application | Description | Status |
|---|---|---|---|
| I-A | PWR UOX | Multiplication factor, spectra and reaction rates calculations for an infinite PWR fuel rod lattice with varying compositions (different enrichments, burnups, cooling-times, presence or absence of actinides -major and minor- and of fission products - major and minor- | Report published in June 1996 |
| I-B | PWR UOX | Depletion calculations for a simple infinite PWR pin-cell lattice. | Report published in January 1994 |
| II-A | PWR UOX | Multiplication factor calculations of an infinite array of PWR fuel with finite axial height. The aim being to study the effect of axial burn-up profile on criticality calculations of PWR fuel storage. | Report published in February 1996 |
| II-B | PWR UOX | Multiplication factor and spatial fission distribution calculations of a realistic PWR spent fuel transport cask including accidental situations. The aim being to further study the effect of axial burn-up profile on criticality calculations. | Report published in May 1998 |
| II-C | PWR UOX | Multiplication factor and fission distribution calculations of a realistic PWR fuel transport cask. The aim being to study the sensitivity to the axial burnup shape. | Report published in September 2008 |
| II-D | PWR UOX | Multiplication factor and fission distribution calculations of a realistic PWR fuel transport cask. The aim being to study control rods effects on spent fuel composition. | Report published in December 2006 |
| II-E | PWR UOX | Study on the impact of changes in the isotopic inventory due to control rod insertions in PWR UO2 fuel assemblies during irradiation on the end effect | Report published in June 2015 |
| III-A | BWR UOX | Criticality calculations of an infinite array of BWR spent fuel assemblies with emphasis on axial burnup and void profiles. | Report published in September 2000 |
| III-B | BWR UOX | Depletion calculations of an array of BWR fuel. | Report published in February 2002 |
| III-C | BWR UOX | Compositions of Spent Fuel Assembly for BUC and Criticality control of damaged fuel. | Report published in March 2016 |
| IV-A | PWR MOX | Reactivity Prediction Calculations for Infinite Arrays of PWR MOX Fuel Pin Cells | Report published in May 2003 |
| IV-B | PWR MOX | Inventory MOX Fuel Depletion Calculations | Report published in May 2003 |
| VI | PWR UOX | Burn-up profile in a VVER-440 assembly | Analysis of results on-going |
| VII | PWR UOX | Study of spent fuel compositions for long-term disposal | Report Published February 2012 |
| VIII | PWR | Reactivity worth of small isotopic samples (FP and actinides) in pile-oscillation experiments | Specifications Distributed |
Last updated: February 2012
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