Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
CSNI2039 ATLAS PROJECT.
last modified: 20-NOV-2020 | catalog | new | search |

CSNI2039 ATLAS PROJECT.

ATLAS PROJECT, The Advanced Thermal-hydraulic Test Loop for Accident Simulation Project

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1. NAME

OECD/ATLAS Project

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2. COMPUTERS

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Program name Package id Status Status date
ATLAS PROJECT CSNI2039/01 Arrived 20-NOV-2020

Machines used:

Package ID Orig. computer Test computer
CSNI2039/01 Many Computers
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3. DESCRIPTION

The main objective of the first phase was to provide experimental data for resolving key LWR thermal-hydraulics safety issues related to multiple high-risk failures and highlighted in particular from the Fukushima Daiichi nuclear power plant accident, by using the ATLAS facility at the Korea Atomic Energy Research Institute (KAERI).

 

The first phase focused in particular on the validation of simulation models and methods for complex phenomena of high safety relevance to thermal-hydraulic transients in DBAs and DECs:

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

  • Facilitated the assessment of codes currently in use for thermal-hydraulic safety analyses, as well as advanced codes under development, including three-dimensional computer 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 programme was intended to provide a valuable and broadly usable database to achieve the above objectives. In phase one, a total of eight to ten tests at the ATLAS facility were proposed to be conducted within five different research topics:

  • prolonged station blackout (SBO)

  • small break loss-of-coolant accident (SBLOCA) during SBO

  • total loss of feedwater (TLOFW)

  • medium-break LOCAs

  • scale-up issues – related to assessing the applicability of small-scale experimental data to full-scale reactors.

 

Participating countries: Belgium, China, Finland, France, Germany, Hungary, India, Japan, Korea, Russian Federation, Spain, Sweden, Switzerland, United Arab Emirates and the United States.

 

Project period: April 2014 to March 2017.

 

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

 

For more detailed information visit https://www.oecd-nea.org/jcms/pl_24812/advanced-thermal-hydraulic-test-loop-for-accident-simulation-atlas-project

 

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9. STATUS
Package ID Status date Status
CSNI2039/01 20-NOV-2020 Masterfiled restricted
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10. REFERENCES
CSNI2039/01, included references:
- K-H. Kang, B-Y. Bae, Y. Park, S. Cho, S-W. Lee and J. Kim:
Final Integration Report of OECD-ATLAS Project (May 2017)
- Ki-Yong CHOI:
Summary Report of the OECD-ATLAS Joint Project
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS

Korea Atomic Energy Research Institute

111 Daedeok-daero 989 beon-gil, Deogjin-dong, Yuseong-gu,

Daejeon

Korea

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16. MATERIAL AVAILABLE
CSNI2039/01
ATLAS tests: data and reports
Facility description reports
Final report
Summary of Q&As for OECD-ATLAS Project
RELAP input
Scaling Analysis Report of the ATLAS Facility
Visualization Tool
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: accident analysis, loop, simulation, thermal hydraulics.