OECD Nuclear Energy Agency (NEA), US Nuclear
Regulatory Commission (NRC),
Penn State University (PSU), Japan Nuclear Safety Organisation (JNES)
NEA Nuclear Science Committee (NSC), NEA Committee on
Safety of Nuclear
Installations (CSNI)
OECD-NEA/US-NRC Benchmark based on
NUPEC BWR Full-size Fine-mesh Bundle Tests
(BFBT)
Files for Participants
Akira INOUE (Tokyo Institute of Technology), Tatsuo KUROSU,
Toshimasa
AOKI, Makoto YAGI (Nuclear Power Engineering Corporation), Toru
MITSUTAKE and Shin-ichi MOROOKA (Nuclear Engineering Lab., Toshiba
Corporation): Void Fraction
Distribution in BWR Fuel Assembly and
Evaluation of Subchannel Code, Journal of NUCLEAR SCIENCE and
TECHNOLOGY, 32[7], pp. 629-640 (July 1995). (PDF format)
OECD/NRC BENCHMARK BASED ON NUPEC BWR FULL-SIZE FINE-MESH
BUNDLE TESTS (BFBT) - Assembly Specifications and Benchmark
Database, October 4, 2004, Incorporated Administrative
Agency Japan Nuclear Energy Safety Organization (JNES), JNES-04N-0015,
[CONFIDENTIAL], (PDF Format), (Word Format)
Templates
for submission of results
(27 February 2006 added
template Phase I Exercise 2 - CFD and other microscopic type results) (13 November 2006 addes Templates for
Phase I Exercise 3 and Phase II Exercise 2)
Additional
information for BFBT Benchmark by Hideaki Utsuno (JNES), 10 May
2006, concerning
- water rod description and modeling
- how and where the flow is entering the bundle
- coordinates for one pixel in relation to the center of the bundle
- 9 densitometer measurements in the horizontal plane for the specified
axial locations
A Group on Guidelines for Use of CFD in Nuclear Reactor Safety
Applications of the Group on Analysis and management of Accidents
of the CSNI meets regularly and they have agree to share the following
reports with the BFBT Group: