The NEA has released version 2 of the Shielding Integral Benchmark Archive and Database (SINBAD), following the migration to a collaborative development environment and a standardised dataset format....

This web page is intended for the description of the nuclear fuel cycle codes that have been used in the recent activities of the Expert Group on Advanced Fuel Cycle Scenarios (EGAFCS), under the gui...

The Advanced Nuclear Cycle Code, ANICCA, is a nuclear fuel cycle simulation code (NFCSC) that has been developed by SCK-CEN as a flexible tool for nuclear fuel cycle studies. ANICCA is able to simula...

NMB4.0 is designed to provide flexibility and an all-in-one packaged nuclear fuel cycle simulation for users as open code. Various ideas have been implemented to improve user-friendliness. The main t...

TR_EVOL (Transition Evolution code) fuel cycle simulator is a tool dedicated to the study of mass balances of advanced transition electronuclear scenarios.

Refined models for best-estimate calculations based on good-quality experimental data can improve the understanding of phenomena and the quantification of margins for operating nuclear power reactors...

This report provides the specification for the uncertainty exercises of the international OECD/NEA, NRC and NUPEC BFBT benchmark problem including the elemental task. The specification was prepared j...

In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for Boiling Water Reactor (BWR) fuel bundles. This international benchmark, bas...

In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for boiling water reactor (BWR) fuel bundles. This international benchmark, bas...

Based on the success of the OECD/NRC BFBT Benchmark, Japan released data based on the NUPEC PWR Sub-channel and Bundle Tests (PSBT) Benchmark and asked Pennsylvania State University (PSU) in the Unit...

21-22 January 2003, Barcelona, Spain