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CSNI2021 ROSA-2.

ROSA-2, Rig-of-safety Assessment Project

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1. NAME OR DESIGNATION

ROSA-2 Project

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2. COMPUTERS
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Program name Package id Status Status date
ROSA-2 CSNI2021/01 Arrived 15-MAY-2014

Machines used:

Package ID Orig. computer Test computer
CSNI2021/01 PC Windows
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3. DESCRIPTION

The OECD/NEA ROSA-2 project aimed to resolve key light water reactor (LWR) thermal-hydraulics safety issues highlighted from the first phase of the project by using the ROSA/large-scale testing facility (LSTF) at the Japan Atomic Energy Agency.

 

In particular, the ROSA-2 Project focused on the validation of simulation models and methods for the following complex phenomena of high-safety relevance for thermal-hydraulic transients in design basis events (DBE) and beyond-DBE:

  • Generated a system-integral and a separate-effect experimental database to validate predictive capability and accuracy of computer codes and models. Thermal-hydraulic phenomena coupled with multi-dimensional flows that might have included mixing, stratification, counter-current flows, parallel-channel flows and oscillatory flows were the main focus of the investigations.

  • Facilitated assessment of codes in use for thermal-hydraulic safety analyses as well as advanced codes under development including three-dimensional computational fluid dynamics (CFD) codes through active involvement of the project partners who maintained and improved the technical competence in thermal-hydraulics for nuclear reactor safety (NRS) evaluations.

 

The experimental program was intended to provide a valuable and broadly usable database to achieve the above cited objectives. The OECD/NEA ROSA-2 Project consisted of six LSTF experiments that mainly included two groups of experiments which are intermediate break loss-of-coolant (LOCA) accidents and steam generator tube rupture (SGTR) accidents. One of the six experiments may have been directed to a different target following a discussion with the project partners.

 

Project period: 01 April 2009-31 March 2013.

 

Project participants

The project was supported by safety organisations, research laboratories and industry from the following countries: Belgium, the Czech Republic, Finland, France, Germany, Hungary, Japan, Republic of Korea, Spain, Sweden, Switzerland, the United Kingdom and the United States.

 

The distribution of this package is restricted to participating countries and subject to prior approval.

 

For more detailed information visit http://www.oecd-nea.org/jointproj/rosa-2.html

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9. STATUS
Package ID Status date Status
CSNI2021/01 15-MAY-2014 Masterfiled restricted
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10. REFERENCES
CSNI2021/01, included references:
- Final Integration Report of OECD/NEA ROSA-2 Project 2009 - 2012 (JAEA),
- Final data reports,
- Participants presentations
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS

Thermohydraulic Safety Research Group

Nuclear Safety Research Center

Japan Atomic Energy Agency (JAEA)

2-4 Shirakata-shirane

Tokai, Ibaraki 319-1195

Japan

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16. MATERIAL AVAILABLE
CSNI2021/01
Final integration report,
Test data and final data reports of the 7 LSTF experiments,
Blind analysis results for Test 1, 2, 5, and 7,
Analysis results by the project participants presented at programme review group
meetings
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: LWR reactors, light-water reactors, safety assessment, thermal hydraulics.