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)
- NUTHOS-6 Special
session on OECD/NRC BFBT Benchmark, Nara-ken New Public Hall,
Nara, Japan, 5 October 2004
- B. Neykov, F. Aydogan, L. Hochreiter, K. Ivanov (PSU), H.
Utsuno, K. Fumio (JNES), E.Sartori (OECD/NEA)
NUPEC BWR FULL-SIZE
FINE-MESH BUNDLE TEST (BFBT) BENCHMARK, Volume I: Specifications
NEA/NSC/DOC(2005)5, Revision
2, May 2005
RESTRICTED DISTRIBUTION Only for BENCHMARK PARTICIPANTS Reproduction
Prohibited
- - Further
explanation 1 on
spacer grid (Fatih Avdogan and Hideaki Utsuno) 10 June 2005
- Further explanation 2 on
spacer grid (Hideaki Utsuno) 15 June 2005
- Answer to Questions
(Hideaki Utsuno) 20 June 2005
- Answer by Hideaki
Utsuno on Queries by Markus Glück, made on 20 June 2005
on
Void_Fraction_Test / Steady_State / 0011-55,
Void_Fraction_Test / Transient / 4102-001~009
- NUPEC BWR FULL-SIZE
FINE-MESH BUNDLE TEST (BFBT) BENCHMARK, Volume I: Specifications, NEA/NSC/DOC(2005)5, Revision
3, 1 July 2005
- List of changes from previous version to
version 3 of BFBT Specification
- Nichrome and Boron Nitride Material Properties
- NUPEC
BWR FULL-SIZE FINE-MESH BUNDLE TEST (BFBT) BENCHMARK, Volume I:
Specifications, NEA/NSC/DOC(2005)5, Revision 4.1,
22 November 2005 - with NO comments
(PDF-Version)
- NUPEC
BWR FULL-SIZE FINE-MESH BUNDLE TEST (BFBT) BENCHMARK, Volume I:
Specifications, NEA/NSC/DOC(2005)5, Revision 4.1,
22 November 2005 - WITH comments
(PDF-Version)
- OECD-NEA/US-NRC/NUPEC
BWR Full-size Fine-mesh Bundle Test
(BFBT)
Benchmark, Volume I: Specifications, B. Neykov, F. Aydogan, L.
Hochreiter, K. Ivanov (PSU), H. Utsuno, F. Kasahara (JNES), E.Sartori
(OECD/NEA), M. Martin (CEA), © OECD 2006, NEA No. 6212,
NEA/NSC/DOC(2005)5, ISBN 92-64-01088-2 (11 August 2006)
- Assembly Types 0, 1, 2, and 3 -
Estimated Grid Spacer Dimensions (Word) (13
February 2006)
- Assembly Type 4 - Estimated Ferrule
Spacer Dimensions (Word) (13
February 2006)
- 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
- Smoothed boundary conditions for
OECD benchmarks of void- and transition boiling transients (13 November 2006)
- Questionnaire for Phase I and
II Exercises to be filled in by Participants (13 November 2006)
- NUPEC BWR FULL-SIZE FINE-MESH BUNDLE TEST (BFBT) BENCHMARK
Volume
II: Uncertainty and Sensitivity Analyses of Void Distribution and
Critical Power - Specification by F. Aydogan, L. Hochreiter, K.
Ivanov (PSU), M. Martin (CEA), H. Utsuno(JNES), and
E.Sartori(OECD/NEA),
NEA/NSC/DOC(2007)21, 15 November 2007,
48 pages (final
draft before printing)
- Answer
to rod displacement issues in BFBT Benchmark(Hideaki Utsuno, JNES) (12 March 2009)
- Chordal
averaged void fraction measurements (Hideaki Utsuno, JNES) (18 March 2009)
OECD-NEA
Benchmark based on
NUPEC PWR Sub-channel Bundle Tests
(PSBT) NEW
- OECD/NEA Benchmark Based on NUPEC PWR Sub-channel and
Bundle Tests (PSBT) - Assembly
Specifications and Benchmark Database,Volume I , (21
April 2009),
Japan Nuclear Energy Safety Organization (JNES),
JNES/SAE-TH08-0019, 48 pages
- OECD/NEA Benchmark Based on NUPEC PWR Sub-channel and
Bundle Tests (PSBT) - Benchmark Database
References to Volume I, (14 April 2009),
Japan Nuclear Energy Safety Organization (JNES),
JNES/SAE-TH08-0019
- [1] Proving
Test on the Reliability for Nuclear Fuel Assemblies, Summary Report of
Proving Tests on the Reliability for Nuclear Power Plant – 1989,
Nuclear Power Engineering Test Center, 1989.
- [2] Hori, K. et al., In
Bundle Void Fraction Measurement of PWR Fuel Assembly, ICONE-2,
Vol.1, pp.69-76, San Francisco, California, 21-24 March 1993.
- [3] Hori, K. et al., Void
Fraction in A Single Channel Simulating One Subchannel of A PWR Fuel
Assembly, Two-Phase Flow Modeling and Experimentation,
pp.1013-1027, 1995.
- [4] Akiyama, M. et al., Reliability
Proving Test on Maximum Thermal Loading of PWR Fuel Assembly, Journal
of Nuclear Science and Technology, Vol. 36, No. 1, p. 47, 1994 (in
Japanese)
- [5]
Pamphlet
of Takasago Engineering Lab. (NUPEC)
- OECD/NEA Benchmark Based on NUPEC PWR Sub-channel and
Bundle Tests (PSBT) - Assembly
Specifications and Benchmark Database,Volume II
(password-encrypted) (17 April 2009)
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Void fraction measurements data
- Steady-state void fraction in
subchannel by CT
measurement
- Steady-state void distribution image in subchannel by CT measurement
- Steady-state void fraction in
rod bundle by chordal measurement
- Steady-state void distribution image in rod bundle by chordal measurement
- Transient void fraction in
rod bundle by chordal measurement
|
1, 2, 3, 4
1, 2
5, 6, 7, 8
5
6
7
8
5T, 6T, 7T
|
1
2
1
3a,
3b
3c,
3d
3e,
3f
3g
1
|
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DNB measurements data
- Steady-state DNB
data in rod bundle
- Steady-state DNB detected location in rod bundle
- Steady-state
fluid temperature distribution in rod bundle
- Transient DNB
data in rod bundle
|
0, 2, 3, 4, 8, 13
4, 8, 13
1
11T, 12T
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4
4
4
4
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Reports from CSNI/GAMA on CFD
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:
These files should not be further distributed.
Contact at OECD/NEA:
OECD/NEA Data Bank
Le Seine-Saint Germain
12 boulevard des Iles
F-92130 Issy-les-Moulineaux
France
Tel: +33 1 45 24 10 72 / 78
Fax: +33 1 45 24 11 10 / 28
Last update: 17 May 2009