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NEA-1731 ZZ-BFBT.

ZZ BFBT, OECD/NEA-US/NRC NUPEC BWR Full-size Fine-mesh Bundle Tests Benchmark

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1. NAME OR DESIGNATION:  ZZ-BFBT.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
ZZ-BFBT-SPECS NEA-1731/02 Tested 03-JUN-2005
ZZ-BFBT NEA-1731/07 Tested 24-JUN-2009

Machines used:

Package ID Orig. computer Test computer
NEA-1731/02 Many Computers PC Windows
NEA-1731/07 Many Computers PC Windows
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3. DESCRIPTION OF BENCHMARK

This international benchmark, based on the NUPEC database, encourages advancement in this uninvestigated field of two-phase flow theory with very important relevance to the nuclear reactor''s safety margins evaluation. Considering the immaturity of the theoretical approach, the benchmark specification is being designed so that it systematically assesses and compares the participants' numerical models on the prediction of detailed void distributions and critical powers. Furthermore, the following points are kept in mind while the benchmark specification is being established:
  
As concerns the numerical model of void distributions, no sound theoretical approach that can be applied to a wide range of geometrical and operating conditions has been developed.
  
In the past decade, experimental and computational technologies have improved tremendously through the study of the two-phase flow structure. Over the next decade, it can be expected that mechanistic approaches will be more widely applied to the complicated two phase fluid phenomena inside fuel bundles.
  
The development of truly mechanistic models for critical power prediction is currently underway. These models must include elementary processes such as void distributions, droplet deposit, liquid film entrainment, etc.
  
The BFBT benchmark consists of two parts (phases), each part consisting of different exercises:
  
Phase 1 - Void Distribution Benchmark
  
Exercise 1 - Steady-state sub-channel grade benchmark
Exercise 2 - Steady-state microscopic grade benchmark
Exercise 3 - Transient macroscopic grade benchmark
  
Phase 2 - Critical Power Benchmark
  
Exercise 1 -Steady-state benchmark
Exercise 2 - Transient benchmark
  
  
ZZ-BFBT-SPECS NEA-1731/02 contains the full details of the BFBT Benchmark Specification as well as the experimental data released.
  
ZZ-BFBT NEA-1731/07 contains the Proceedings of First Workshop (BFBT1), Second Workshop (BFBT2), Third Workshop (BFBT3), Fourth Workshop (BFBT4), Fifth Workshop (BFBT5) and Sixth Workshop (BFBT6).
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9. STATUS
Package ID Status date Status
NEA-1731/02 03-JUN-2005 Tested restricted
NEA-1731/07 24-JUN-2009 Tested restricted
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10. REFERENCES
NEA-1731/02, included references:
- 1. 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 Version 02 May 2005
(restricted to participants)
- 2. 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).
- 3. OECD/NRC Benchmark Based on Nupec BWR Full-Size Fine-Mesh Bundle Tests
(BFBT) Assembly Specifications and Benchmark Database
JNES-04N-0015 (October 4, 2004)
NEA-1731/07, included references:
- Proceedings of the OECD-NEA/US-NRC Benchmark based on NUPEC BWR Full-size
Fine-mesh Bundle Tests (BFBT)
- First Workshop (BFBT-1), 4th October 2004,
Nara, Japan, Hosted by Japan Nuclear Energy Safety Organization (JNES),
NEA/NSC/DOC(2004)15
- Second Workshop (BFBT-2), 27-29 June 2005,
Reber Building, University Park, PA, USA, hosted by the Pennsylvania State
University (PSU)
- Third Workshop (BFBT3), 26-27 April 2006
Hotel Duomo, Pisa, Italy, hosted by the University of Pisa
- Fourth Workshop (BFBT4), 8-9 May 2007
Paris, France, Hosted by CEA (France)
- Fifth Workshop (BFBT5), 31 March to 1 April 2008
Garching, Germany, Hosted by GRS
- Sixth Workshop (BFBT6), 27-28 April 2009
University Park, State College, PA, USA, Hosted by PSU
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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13. SOFTWARE REQUIREMENTS:  HTML Browser, Acrobat Reader, Microsoft Excel.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHORS

B. Neykov, F. Aydogan, L. Hochreiter, K. Ivanov
Nuclear Engineering Program
The Pennsylvania State University
University Park, PA 16802, USA
  
H. Utsuno, K. Fumio
Japan Nuclear Energy Safety Organization
Kamiya-cho MT Bldg., 4-3-20, Toranomon, Minato-ku,
Tokyo, 105-0001, Japan
  
E.Sartori
OECD Nuclear Energy Agency
12 boulevard des Iles
92130 Issy les Moulineaux, France
  
Sponsors:
US Nuclear Regulatory Commission, and OECD Nuclear Energy Agency (NEA)
Co-organisers:
NEA Nuclear Science Committee (NSC), NEA Committee on Safety of Nuclear Installations (CSNI)
  
This information is restricted to benchmark participants.
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16. MATERIAL AVAILABLE
NEA-1731/02
Benchmark Specification and experimental data
- readme-first.txt
- BFBT-Conditions-for-Release.pdf
- CD-ROM Title.DOC
- directory /JNES-04N-0015/ (Reports)
- directory /Specification/ with spacer information
- directory /Critical Power/ sub /Steady State/ sub /Transient/
- directory /Void Distribution/  sub /Steady State/ sub /Transient/

NEA-1731/07
Proceedings of First (BFBT1), second (BFBT2), third Workshop (BFBT3), fifth
WorkshoP (BFBT5) and sixth Workshop (BFBT6)
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: boiling water reactor, coolants, thermal hydraulics, transients, two-phase flow.