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

1. 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)
2. 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)
3. NUTHOS-6 Special session on  OECD/NRC BFBT Benchmark, Nara-ken New Public Hall, Nara, Japan, 5 October 2004
4. 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
   
5. - 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
6. 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
7. 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)

8. 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)

9. 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)
10. Assembly Types 0, 1, 2, and 3 - Estimated Grid Spacer Dimensions (Word) (13 February 2006)
11. Assembly Type 4 - Estimated Ferrule Spacer Dimensions (Word) (13 February 2006)
12. 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)
13. 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
14. Smoothed boundary conditions for OECD benchmarks of void- and transition boiling transients (13 November 2006)
15. Questionnaire for Phase I and II Exercises to be filled in by Participants (13 November 2006)
16. 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)
17. Answer to rod displacement issues in BFBT Benchmark(Hideaki Utsuno, JNES) (12 March 2009)
18. Chordal averaged void fraction measurements  (Hideaki Utsuno, JNES) (18 March 2009)

See PSBT for more information - Conditions for releasing PSBT data

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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:

• Recommendations on Guidelines for the Use of CFD in Nuclear Reactor Safety Applications NEA/SEN/SIN/AMA(2005)2
• Assessment of CFD Codes for Nuclear Reactor Safety Problems NEA/SEN/SIN/AMA(2005)3
• Best Practice Guidelines for the use of CFD in Nuclear Reactor Safety Applications, OECD Nuclear Enegy Agency, Committee on the Safety of Nuclear Installations NEA/CSNI/R(2007)5, 15-May-2007
  

These files should not be further distributed.
    

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Last reviewed: 2 December 2011