Major Thermal-Hydraulic Phenomena Found During Atlas Lbloca Reflood Tests for an Advanced Pressurized Water Reactor Apr1400

Park, Hyun-Sik; Choi, Ki-Yong; Cho, Seok; Kang, Kyoung-Ho; Kim, Yeon-Sik

doi:10.5516/net.2011.43.3.257

Cited by 6 publications

(4 citation statements)

References 13 publications

(16 reference statements)

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“…The main objective of the Phase 2 tests was to investigate the thermal-hydraulic characteristics during an entire reflood period to provide reliable data to help validate the LBLOCA analysis methodology for the APR1400. Among the whole test matrix of the LBLOCA reflood tests, LB-CL-09, LB-CL-11, LB-CL-14, and LB-CL-15 were seriously analyzed to support the licensing process of the APR1400 in Korea, and their results dealing with the experimental results and analysis were already published [12][13][14][15]; only the major outcomes are summarized in this paper. Key test matrix for the LBLOCA tests is shown in Table 2.…”

Section: Major Outcomes Of the Previous Ietsmentioning

confidence: 99%

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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: Major Outcomes Of the Previous Ietsmentioning

confidence: 99%

“…The core heaters were quenched in the order of the middle region, center region, and outer region. Figure 7 shows a typical ECC bypass ratio obtained from the LB-CL-11 test [14]. The ECC bypass ratio is defined as follows:…”

Section: Major Outcomes Of the Previous Ietsmentioning

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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“…In the first phase of the ATLAS operation, a series of integral effect tests on the LBLOCA reflood phenomena were carried out in order to investigate the thermal-hydraulic phenomenon during the reflood phase of the LBLOCA by using ATLAS. [4][5][6] Afterward, a series of DVI line break tests 7) were performed by varying the break size from 5 to 100% and, subsequently, a series of cold-leg break tests 8) were performed to include sensitivity tests on the break size, break location, and the emergency core cooling water injection configuration. These SBLOCA tests were performed to investigate the performance of the DVI method for ECC water delivery adopted for the APR1400 with the ATLAS.…”

Section: Introductionmentioning

confidence: 99%

Counterpart Tests of SBLOCA on the Effect of Break Location with the ATLAS: DVI Nozzle versus Cold-Leg Breaks

PARK

Choi

Cho

et al. 2011

J. Nucl. Sci. Technol.

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Results from two integral effect tests were compared to discuss the effect of break location between the direct vessel injection (DVI) nozzle and cold leg during the small-break loss of coolant accident (SBLOCA) scenario. One is the SB-DVI-09 test for a 6-inch (50% break area of a DVI nozzle) DVI line break and the other is the SB-CL-06 test for an equivalent break size of cold leg. Both counterpart tests were performed with the same control logic and initial/boundary conditions except for different break locations of the DVI line and cold leg. Experimental results showed that the maximum heater surface temperature increased more with the broken DVI nozzle (SB-DVI-09) than with the broken cold leg (SB-CL-06) due to the delayed and simultaneous occurrence of the loop seal clearing and the momentary decrease in the collapsed water level in the core region.

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“…[4][5][6] Afterward, a series of DVI line break tests 7) were performed by varying the break size from 5 to 100% and, subsequently, a series of cold-leg break tests 8) were performed to include sensitivity tests on the break size, break location, and the emergency core cooling water injection configuration. These SBLOCA tests were performed to investigate the performance of the DVI method for ECC water delivery adopted for the APR1400 with the ATLAS.…”

Section: Introductionmentioning

confidence: 99%