KAERI Integral Effect Test Program and the ATLAS Design

Baek, Won-Pil; Song, Chul-Hwa; Yun, Byong-Jo; Kwon, Tae-Soon; Moon, Sungmo; Lee, Sung–Jae

doi:10.13182/nt05-a3669

Cited by 63 publications

(14 citation statements)

References 2 publications

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“…The ATLAS experimental facility [10] was designed according to the well-known scaling method suggested by Ishii and Kataoka [11] to simulate various test scenarios as realistically as possible. It is a half-height and 1/288 volume scaled test facility with respect to the APR1400 (Advanced Power Reactor 1400 MWe).…”

Section: Description Of the Atlas Facilitymentioning

confidence: 99%

The MARS Simulation of the ATLAS Main Steam Line Break Experiment

Ha¹,

Yun²,

Jeong³

2014

Journal of Energy Engineering

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A main steam line break (MSLB) test at the ATLAS facility was simulated using the best-estimate thermal-hydraulic system code, MARS-KS. This has been performed as an activity at the third domestic standard problem for code benchmark (DSP-03) that has been organized by Korea Atomic Energy Research Institute (KAERI). The results of the MSLB experiment and the MARS input data prepared for the previous DSP-02 using the ATLAS facility were provided to participants. The preliminary MSLB simulation using the base input data, however, showed unphysical results in the primary-to-secondary heat transfer. To resolve the problems, some improvements were implemented in the MARS input modelling. These include the use of fine meshes for the bottom region of the steam generator secondary side and proper thermal-hydraulics calculation options. Other input model improvements in the heat loss and the flow restrictor models were also made and the results were investigated in detail. From the results of simulations, the limitations and further improvement areas of the MARS code were identified.

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Section: Description Of the Atlas Facilitymentioning

confidence: 99%

The MARS Simulation of the ATLAS Main Steam Line Break Experiment

Ha¹,

Yun²,

Jeong³

2014

Journal of Energy Engineering

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“…It has been operated in order to investigate major design basis accidents and operational transients for a 1400 MWe pressurized water reactor, APR1400, which was developed by the Korean industry [ref. [4][5]. The ATLAS also incorporates several specific design characteristics of a 1000 MWe-class Korean standard nuclear power plant, OPR1000 (Optimized Power Reactor 1000 MWe).…”

Section: Description Of Atlas Facilitymentioning

confidence: 99%

International Standard Problem 50: The University of Pisa Contribution

Cherubini¹,

Lazzerini²,

Giannotti³

et al. 2012

Nuclear Engineering and Technology

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“…The separate effect test, PASCAL (PAFS Condensing Heat Removal Assessment Loop), is in progress to experimentally investigate the condensation heat transfer and natural convection phenomena in PAFS. The integral effect test is being performed to confirm the operational performance of the PAFS coupled with the other reactor coolant systems (RCS) using the thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic test Loop for Accident Simulation) [4]. This paper summarizes the up-to-date experimental results of the separate effect test and the integral effect test for PAFS from a cooling and operational performance point of view.…”

Section: Introductionmentioning

confidence: 99%