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NEA-1849 ZZ-PSBT.

ZZ PSBT, NUPEC PWR Sub-channel Bundle Tests Benchmark

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1. NAME OR DESIGNATION:  ZZ-PSBT.
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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-PSBT-PROCS NEA-1849/04 Arrived 18-NOV-2011
ZZ-PSBT-SPECS NEA-1849/05 Arrived 16-NOV-2011

Machines used:

Package ID Orig. computer Test computer
NEA-1849/04 Many Computers PC Windows
NEA-1849/05 Many Computers PC Windows
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3. DESCRIPTION OF BENCHMARK

An approach, similar to the OECD/NRC BFBT benchmark (NEA-1731), is adopted by dividing the PSBT benchmark activity in Phases. Each Phase consists of several Exercises. It is desirable also to plan the benchmark specification to accept as many potential numerical approaches as possible.
  
The NUPEC PSBT benchmark will consist of two Phases, with each Phase consisting of three Exercises. The Phase I is the Void distribution benchmark, and Phase II is the DNB benchmark.  The participants can choose either of the following two Phases and any of the Exercises within the Phases to take part and contribute. The preliminary indications show that a sufficient number of participants will attempt both Phases with different numerical approaches.
  
In addition to the measured experimental data and the relevant boundary conditions, the detailed geometrical data of mock-up assemblies, spacers and the test loop will be included as far as possible in the specification in order to allow a wide range of numerical modelling. Below is the definition of the corresponding Exercises of the two Phases:
  
Phase I: Void Distribution Benchmark
  
Exercise I-1: Steady-State Single Sub-channel Benchmark
  
The goal of this exercise is to benchmark the subchannel, meso- and microscopic numerical approaches. The experimental data includes CT scan measurements of the subchannel averaged void fraction in four subchannel types: typical central, central with a guide tube, side, and corner. In addition, graphical images of the void distribution within the typical central subchannels and central subchannel with guide tube are available. The test cases are selected at PWR rated conditions. Different types of single subchannel test assemblies are used to investigate the effect of geometry on phenomenon in concern.
  
Exercise I-2: Steady-State Bundle Benchmark
  
This exercise is designed for benchmarking meso-scopic numerical approaches. The experimental data includes X-ray densitometer measurements of void fraction (chordal averaged over the four central subchannels) at three axial elevations along the bundle length and graphical images of the bundle void distribution. The test cases for this exercise are chosen at PWR rated conditions and deviations of quality from the rated conditions.
  
Exercise I-3: Transient Bundle Benchmark
  
NUPEC PSBT database includes simulation of four representative transients of PWRs; power increase, flow reduction, depressurization, and temperature increase. All four transients are selected as benchmark cases. The experimental data includes time histories of X-ray densitometer measurements of void fraction (chordal averaged over the four central subchannels) at three axial elevations along the bundle length for four transient scenarios: power increase; flow reduction; depressurization; and temperature increase. Exercise 3 of Phase I is designed for benchmarking subchannel numerical approaches.
  
Exercise I-4: Pressure Drop Benchmark
  
This exercise is designed for performing code-to-code comparisons concerning axial pressure drop. Although no empirical data is available, code results will be compared with relevant graphical data.
  
Phase II: DNB Benchmark
  
Exercise II-1: Steady-State Fluid Temperature Benchmark
  
Exercise 1 of Phase II is designed to assess the thermal-hydraulic codes' capabilities of predicting the exit coolant temperature. The experimental data includes measurements of the subchannel-averaged fluid outlet temperatures.
  
Exercise II-2: Steady-State DNB Benchmark
  
The goal of Exercise 2 of Phase II is to assess the thermal-hydraulic codes' capabilities of correct prediction of DNB along rod bundles. The experimental data includes the power at which DNB occurs and the corresponding locations in the bundle.
  
Exercise II-3: Transient DNB Benchmark
  
Exercise 3 of Phase II is designed to enhance the currently underway development of truly mechanistic models for DNB prediction during the four postulated transients in PWRs. The experimental data includes the time histories of the boundary conditions and the detected DNB time for four transient scenarios: power increase; flow reduction; depressurization; and temperature increase.
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ZZ-PSBT-PROCS NEA-1849/04 contains the electronic documents, the summary of the Sixth Workshop on the NUPEC BFBT, and the Final Problem Specifications for PSBT.
  
ZZ-PSBT-SPECS NEA-1849/05 contains the documents of NEA-1849/04 and the PSBT database in Excel format, accessible to only the participants in the benchmarks.
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9. STATUS
Package ID Status date Status
NEA-1849/04 18-NOV-2011 Masterfiled restricted
NEA-1849/05 16-NOV-2011 Masterfiled restricted
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10. REFERENCES
NEA-1849/04, included references:
- PSBT-1: April 12-13, 2010 - Hosted by the University of Pisa, Italy.
- PSBT-2: April 11-12, 2011 - Hosted by the Royal Institute of Technology
(Kungliga Tekniska Hogskolan, KTH) Stockholm, Sweden.
NEA-1849/05, included references:
1. 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, 49 pages

2. OECD/NEA Benchmark Based on NUPEC PWR Sub-channel and Bundle Tests (PSBT)
Assembly Specifications and Benchmark Database, Vol. I Addendum (21 June 2010),
Japan Nuclear Energy Safety Organization (JNES), JNES/SAE-TH08-0019

3. 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)

4. A. Rubin, A. Schoedel, M. Avramova: OECD/NRC Benchmark Based on NUPEC PWR
Subchannel and Bundle Tests; Volume I: Experimental Database and Final Problem
Specifications, NEA/NSC/DOC(2010)1 (November 2010)

5. OECD/NEA Benchmark Based on NUPEC PWR Sub-channel and Bundle Tests (PSBT)
Appendix A: Measurement diagram of the test loop of PSBT (November 2010)

6. OECD/NEA Benchmark Based on NUPEC PWR Sub-channel and Bundle Tests (PSBT)
Appendix B: Drawings of the test vessel of PSBT (November 2010)

7. OECD/NEA Benchmark Based on NUPEC PWR Sub-channel and Bundle Tests (PSBT)
Assembly Specifications and Benchmark Database, Volume II (+Template - Phase II
DNB) (17 April 2009)

8. OECD/NRC Benchmark based on NUPEC PWR Sub-channel and Bundle Tests (PSBT)
First Workshop (PSBT-1), held in Pisa, Italy from April 12-13, 2010, hosted by
the San Piero a Grado Nuclear Research Group, University of Pisa.

9. OECD/NRC Benchmark based on NUPEC PWR Sub-channel and Bundle Tests (PSBT)
Second Workshop (PSBT-2), held in Stockholm, from April 11-12, 2011, hosted by
the Royal Institute of Technology (Kungliga Tekniska Hogskolan, KTH).
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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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15. NAME AND ESTABLISHMENT OF AUTHORS

Dr. Maria AVRAMOVA
Assistant Professor
Associate Director of RDFMG
Nuclear Engineering Program
The Pennsylvania State University
231 Reber Bldg
University Park, PA 16802, USA
  
Dr. Hideaki UTSUNO
Safety Analysis and Evaluation Division
Japan Nuclear Energy Safety Organization (JNES)
Kamiya-cho MT Bldg.,
4-3-20, Toranomon, Minato-ku,
Tokyo, 105-0001, Japan
  
Sponsors: OECD Nuclear Energy Agency (NEA)
Co-organisers:
NEA Nuclear Science Committee (NSC), NEA Committee on Safety of Nuclear Installations (CSNI)
Penn State University (PSU), Japan Nuclear Safety Organisation (JNES),
and US Nuclear Regulatory Commission (US NRC)
  
-------- This information is restricted to benchmark participants
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16. MATERIAL AVAILABLE
NEA-1849/05
1. 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, 49 pages

2. OECD/NEA Benchmark Based on NUPEC PWR Sub-channel and Bundle Tests (PSBT)

Assembly Specifications and Benchmark Database, Vol. I Addendum (21 June 2010),
Japan Nuclear Energy Safety Organization (JNES), JNES/SAE-TH08-0019

3. 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)

4. A. Rubin, A. Schoedel, M. Avramova: OECD/NRC Benchmark Based on NUPEC PWR
Subchannel and Bundle Tests; Volume I: Experimental Database and Final Problem
Specifications, NEA/NSC/DOC(2010)1 (November 2010)

5. OECD/NEA Benchmark Based on NUPEC PWR Sub-channel and Bundle Tests (PSBT)

Appendix A: Measurement diagram of the test loop of PSBT (November 2010)

6. OECD/NEA Benchmark Based on NUPEC PWR Sub-channel and Bundle Tests (PSBT)

Appendix B: Drawings of the test vessel of PSBT (November 2010)

7. OECD/NEA Benchmark Based on NUPEC PWR Sub-channel and Bundle Tests (PSBT)

Assembly Specifications and Benchmark Database, Volume II (+Template - Phase II
DNB) (17 April 2009)

8. OECD/NRC Benchmark based on NUPEC PWR Sub-channel and Bundle Tests (PSBT)
First Workshop (PSBT-1), held in Pisa, Italy from April 12-13, 2010, hosted by
the San Piero a Grado Nuclear Research Group, University of Pisa.

9. OECD/NRC Benchmark based on NUPEC PWR Sub-channel and Bundle Tests (PSBT)
Second Workshop (PSBT-2), held in Stockholm, from April 11-12, 2011, hosted by
the Royal Institute of Technology (Kungliga Tekniska Hogskolan, KTH).
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: coolants, departure from nucleate boiling, pressurized water reactor, thermal hydraulics, transients, void fraction.