The three-level scaling approach with application to the Purdue University Multi-Dimensional Integral Test Assembly (PUMA)

Ishii, Mamoru; Revankar, Shripad T.; Leonardi, Tauna; Dowlati, R.; Bertodano, Martín López de; Babelli, I.; Wang, W.; Pokharna, Himanshu; Ransom, V.H.; Viskanta, R.; Han, Jeong‐Won

doi:10.1016/s0029-5493(98)00222-2

Cited by 112 publications

(13 citation statements)

References 18 publications

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“…The three-level scaling methodology which consists of integral scaling, boundary flow scaling, and local phenomena scaling proposed by Ishii et al [7] was applied to the design of ATLAS. There have been plenty of discussions concerning the height scaling, and finally the 1/2 height scaling was chosen based on the following key rationales [1].…”

Section: Scaling Methodology Of the Atlasmentioning

confidence: 99%

Major Achievements and Prospect of the ATLAS Integral Effect Tests

Choi

Kim

Song

et al. 2012

Science and Technology of Nuclear Installations

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A large-scale thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation), has been operated by KAERI. The reference plant of ATLAS is the APR1400 (Advanced Power Reactor, 1400 MWe). Since 2007, an extensive series of experimental works were successfully carried out, including large break loss of coolant accident tests, small break loss of coolant accident tests at various break locations, steam generator tube rupture tests, feed line break tests, and steam line break tests. These tests contributed toward an understanding of the unique thermal-hydraulic behavior, resolving the safety-related concerns and providing validation data for evaluation of the safety analysis codes and methodology for the advanced pressurized water reactor, APR1400. Major discoveries and lessons found in the past integral effect tests are summarized in this paper. As the demand for integral effect tests is on the rise due to the active national nuclear R&D program in Korea, the future prospects of the application of the ATLAS facility are also discussed.

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Section: Scaling Methodology Of the Atlasmentioning

confidence: 99%

Major Achievements and Prospect of the ATLAS Integral Effect Tests

Choi

Kim

Song

et al. 2012

Science and Technology of Nuclear Installations

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“…They also established the methodology to achieve desired objectives. The bulk of the material included in this section is provided by Kocamustafaogullari and Ishii (1983); Ishii and Kataoka (1984); Ishii et al (1998);Ransom, Wang, and Ishii (1998); Vijayan and Austregesilo (1994); Yadigaroglu and Zeller (1994); Wulff (1996); Reyes and Hochreiter (1998); Reyes (2007); and Zuber (2001).…”

Section: Scaling Analysis For Scale-down Systemsmentioning

confidence: 99%

Conceptual Design of Forced Convection Molten Salt Heat Transfer Testing Loop

Sohal¹,

Sabharwall²,

Calderoni³

et al. 2010

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This report develops a proposal to design and construct a forced convection test loop. A detailed test plan will then be conducted to obtain data on heat transfer, thermodynamic, and corrosion characteristics of the molten salts and fluid-solid interaction. In particular, this report outlines an experimental research and development test plan. The most important initial requirement for heat transfer test of molten salt systems is the establishment of reference coolant materials to use in the experiments. An earlier report produced within the same project highlighted how thermophysical properties of the materials that directly impact the heat transfer behavior are strongly correlated to the composition and impurities concentration of the melt. It is therefore essential to establish laboratory techniques that can measure the melt composition, and to develop purification methods that would allow the production of large quantities of coolant with the desired purity. A companion report describes the options available to reach such objectives. In particular, that report outlines an experimental research and development test plan that would include following steps:• Molten salts: The candidate molten salts for investigation will be selected.• Materials of construction: Materials of construction for the test loop, heat exchangers, and fluid-solid corrosion tests in the test loop will also be selected.• Scaling analysis: Scaling analysis to design the test loop will be performed.• Test plan: A comprehensive test plan to include all the tests that are being planned in the short and long term time frame will be developed.• Design the test loop: The forced convection test loop will be designed including extensive mechanical design, instrument selection, data acquisition system, safety requirements, and related precautionary measures.• Fabricate the test loop.

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“….). " [5], (b) intrinsic limitations of thermalhydraulic codes, namely, the simulation of two-phase flow regime transitions and the impossibility of qualifying their closure equations under transient and nondeveloped flow conditions [6].…”

Section: Introductionmentioning

confidence: 99%

“…Along these lines, several scaling analysis philosophies have been developed (H2TS [7,8]) together with the Ishii three-level scaling approach [5]. Such developments have been applied in the design of new test facilities (APEX [9] and PUMA [5]) in order to identify and evaluate scaling distortion on experimental data. Furthermore, there is still a lack of a global response on the subject of scaling code capabilities to extend the experience acquired through experiments to the use of BEPU calculations for the licensing of NPPs.…”

Section: Introductionmentioning

confidence: 99%

The Use of System Codes in Scaling Studies: Relevant Techniques for Qualifying NPP Nodalizations for Particular Scenarios

Martinez-Quiroga

Reventós

2014

Science and Technology of Nuclear Installations

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System codes along with necessary nodalizations are valuable tools for thermal hydraulic safety analysis. Qualifying both codes and nodalizations is an essential step prior to their use in any significant study involving code calculations. Since most existing experimental data come from tests performed on the small scale, any qualification process must therefore address scale considerations. This paper describes the methodology developed at the Technical University of Catalonia in order to contribute to the qualification of Nuclear Power Plant nodalizations by means of scale disquisitions. The techniques that are presented include the so-calledKv-scaled calculation approach as well as the use of “hybrid nodalizations” and “scaled-up nodalizations.” These methods have revealed themselves to be very helpful in producing the required qualification and in promoting further improvements in nodalization. The paper explains both the concepts and the general guidelines of the method, while an accompanying paper will complete the presentation of the methodology as well as showing the results of the analysis of scaling discrepancies that appeared during the posttest simulations of PKL-LSTF counterpart tests performed on the PKL-III and ROSA-2 OECD/NEA Projects. Both articles together produce the complete description of the methodology that has been developed in the framework of the use of NPP nodalizations in the support to plant operation and control.

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The three-level scaling approach with application to the Purdue University Multi-Dimensional Integral Test Assembly (PUMA)

Cited by 112 publications

References 18 publications

Major Achievements and Prospect of the ATLAS Integral Effect Tests

Major Achievements and Prospect of the ATLAS Integral Effect Tests

Conceptual Design of Forced Convection Molten Salt Heat Transfer Testing Loop

The Use of System Codes in Scaling Studies: Relevant Techniques for Qualifying NPP Nodalizations for Particular Scenarios

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