@inproceedings{181afd8b387e4411847fb70cee4970c5,
title = "Relap5-3d{\textcopyright} analysis of OECD-NEA/NRC BFBT benchmark",
abstract = "OECD-NEA and the NRC organized and sponsored the BWR Fuel Bundle Test (BFBT) Benchmark with the main purpose of assessing sub-channel and Computational Fluid Dynamic codes capabilities in estimating relevant thermal-hydraulics parameters like void fraction and critical power for a BWR boiling channel. The assessment activity is performed comparing the code calculation results with the experimental data at steady state and transient conditions available through the Japanese Nuclear Power Engineering Corporation (NUPEC). In this framework, the San Piero a Grado Nuclear Research Group (GRNSPG) of the University of Pisa (UNIPI) developed a RELAP5-3D",
keywords = "BFBT, MULTID, RELAP, Sub-channel, Void",
author = "A. Kovtonyuk and A. Petruzzi and C. Parisi and F. D'Auria",
year = "2007",
language = "English",
isbn = "0894480588",
series = "Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12",
booktitle = "Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12",
note = "12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12 ; Conference date: 30-09-2007 Through 04-10-2007",
}