Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1

Jeong, Jae Jun; Ha, Kwang Soon; Chung, Bub Dong; Lee, W.J.

doi:10.1016/s0306-4549(99)00039-0

Cited by 226 publications

(48 citation statements)

References 4 publications

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“…In the ATLAS test facility, a total of 1,236 instrumentations are installed for the measurement of local thermal-hydraulic conditions, such as temperature, static pressure, differential pressure, water level, flow rate, mass, power, etc. The Table 1.…”

Section: Description Of the Atlas Facilitymentioning

confidence: 99%

“…For a realistic analysis of thermal-hydraulic transients in light water reactors, KAERI has developed the best-estimate system code, MARS [1,2]. The code has been verified and, thereafter, extensively validated using a wide range of two-phase flow experiments at various facilities, which include a number of both separate effect test and integral effect tests.…”

Section: Introductionmentioning

confidence: 99%

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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%

Section: Introductionmentioning

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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“…The system code, MARS [3], was chosen for this coupling because its hydrodynamic model adopts a two-fluid model for a two-phase flow and its numerical scheme is similar to the corrector step of the CUPID code. Referring to the previous experiences [31], the MARS-CUPID coupling was performed.…”

Section: Coupling Algorithmmentioning

confidence: 99%

“…However, the two-phase CFD simulation has been challenging up to now mainly because of insufficient physical models for a two-phase flow in the CFD scale. Most of the current physical models for a two-phase flow have been developed for system codes, such as MARS [3], REALP5 [4] and CATHARE [5], which adopt onedimensional governing equations. In addition, the numerical solution methods of current CFD codes are sometimes not efficient in dealing with two-phase flows because interface mass, momentum and energy transfer terms are usually treated in an explicit manner as non-linear source terms in the governing equations.…”

Section: Introductionmentioning

confidence: 99%

Multi-Scale Thermal-Hydraulic Analysis of PWRS Using the Cupid Code

Yoon¹,

Cho²,

Lee³

et al. 2012

Nuclear Engineering and Technology

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“…The MARS code, 12) which integrates the RELAP5/MOD3 and COBRA-TF codes, was developed by KAERI. It is important to compare both results in terms of validations of the MARS code and predictions of the thermal hydraulics of the prototype reactor (REX-10).…”

Section: Mars Codementioning

confidence: 99%

Transient Analysis of Natural Circulation Nuclear Reactor REX-10

Jang

Kim

Jeun

2011

Journal of Nuclear Science and Technology

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As research regarding small-and medium-sized nuclear reactors (SMRs) has rapidly increased worldwide, the Regional Energy Research Institute for Next Generation (RERI) is designing a new conceptual nuclear reactor, called the Regional Energy rX-10MW t (REX-10). The REX-10 is an integral-type nuclear reactor and adopts natural circulation for heat removal. Since the REX-10 is designed for district heating and small-scale power generation near residential areas, it has to guarantee safety under all circumstances. Thus, the REX-10 Test Facility (RTF) is designed to evaluate the natural circulation behavior in the REX-10. On the basis of a theoretical model and reactor safety, two experimental parameters (heater power and feedwater flow rate) were chosen and various transient experiments are conducted. As a result of six transient experiments, the RTF guarantees safety against abrupt changes in the experimental parameters. Furthermore, all the experiments are simulated by using the MARS code. In most cases, the results of the MARS code show good agreement with the experimental results. However, in case of the chiller trip, the MARS code overestimates the temperature and generates a fluctuation of the primary flow. However, both results show a similar trend after the fluctuation is finished.

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Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1

Cited by 226 publications

References 4 publications

The MARS Simulation of the ATLAS Main Steam Line Break Experiment

The MARS Simulation of the ATLAS Main Steam Line Break Experiment

Multi-Scale Thermal-Hydraulic Analysis of PWRS Using the Cupid Code

Transient Analysis of Natural Circulation Nuclear Reactor REX-10

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