6 October 2002, Seoul, Korea

Rossendorf (Dresden), Germany, 28-30 May 2002

Attitudes towards plutonium management vary from country to country and from utility to utility: some regard plutonium as a liability and others as a valuable source of energy.

The purpose of this st...

The OECD/NEA Task Force on Computing Radiation Dose and Modelling of Radiation-Induced Degradation of Reactor Components (TFRDD) launched two international blind intercomparison exercises to examine ...

The OECD/NEA Nuclear Science Committee Task Force on Computing Radiation Dose and Modelling of Radiation-induced Degradation of Reactor Components was set up in November 1995 in response to a request...

In this benchmark exercise the goal is to test the current state-of-the-art two-dimensional methods of calculating neutron flux to reactor components against the measured data of the VENUS-1 critical...

Average fuel burn-up in light water reactors (LWRs) has steadily increased with time as technological advances have been made. The practical limit is currently in the region of 50 GWd/t. The main dri...

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...

Twelfth Workshop Proceedings, Batavia, Illinois, United States, 28-30 April 2014

Proceedings of the Fourteenth Workshop, 30 October-2 November 2018, Gyeongju, Korea.

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...

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...

This report defines the “OECD/NEA/NSC PBMR Coupled Neutronics/Thermal-hydraulics Transient Benchmark of the PBMR-400 Core Design”. This chapter gives more information on the day-to-day management of ...

Recently developed best-estimate computer code systems for modelling 3-D coupled neutronics/thermal-hydraulics transients in nuclear reactors need to be validated against results from experiments and...

In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...

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...