Reactor safety issues resolved by the 2D/3D Program. International Agreement Report

Damerell, P.S.; Simons, J.W.

doi:10.2172/10177080

Cited by 28 publications

(5 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…When the CCFL occurs, the mass and heat transfer between gas and liquid phases reduces, and a water pool forms. This phenomenon prevents the core from cooling such that the fuel temperature rapidly increases [7]. Therefore, studies on CCF and CCFL are essential for proper nuclear reactor safety.…”

Section: Introductionmentioning

confidence: 99%

Assessment of TRACE CCFL Model with SBLOCA Experiment of IIST Facility

Yang

Wang

Lin

et al. 2012

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

In this paper, the TRACE model for IIST facility is developed and verified with the Small Break loss of coolant accident (SBLOCA) experiment of IIST (Institute of Nuclear Energy Research Integral System Test) facility. By using the Wallis and Kutateladze correlations of countercurrent flow limitation (CCFL) model, the TRACE analyses results, such as break flow rate, primary pressure, and the temperature of cold-leg and hot-leg, are consistent with the IIST data. The results show the Kutateladze correlation of CCFL model can well predict the SBLOCA behavior and present good agreement with IIST experiment data in this paper. Besides, the sensitivity study results of Kutateladze correlation in CCFL model are verified and compared with the IIST data.

show abstract

Section: Introductionmentioning

confidence: 99%

Assessment of TRACE CCFL Model with SBLOCA Experiment of IIST Facility

Yang

Wang

Lin

et al. 2012

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

show abstract

“…The droplets entrained into the upper plenum can be carried over by the steam flow to the hot-legs and steam generator (SG). The vaporization of droplets in the SG U-tubes contributes to the steam binding problem and degrades core cooling (Damerell and Simons, 1993).…”

Section: Introductionmentioning

confidence: 99%

Droplet de-entrainment by inertial impaction on vertical rods in an air-droplet mixture flow

Lee

Kim

et al. 2006

Nuclear Engineering and Design

View full text Add to dashboard Cite

“…6) The multidimensional phenomena in the DVI system during the reflood phase had been investigated in the UPTF Test 21-D experiment. [7][8][9] From this full scale experiment, an insight was gained on the bypass phenomena occurring in the DVI mode. However, it was still difficult to interpret from the experiment what flow patterns existed and what the detailed mechanism of the ECC bypass was.…”

Section: Introductionmentioning

confidence: 99%

Experimental Study for Multidimensional ECC Behaviors in Downcomer Ann with Direct Vessel Injection Mode during the LBLOCA Reflood Phase

Cho

Yun

Song

et al. 2005

Journal of Nuclear Science and Technology

View full text Add to dashboard Cite

For the assessment of the multidimensional safety analysis codes various investigations have been performed to provide detailed information for the ECC (Emergency Core Coolant) behavior in a downcomer annulus. In the present study, the multidimensional ECC bypass phenomena in the downcomer annuli of the UPTF (Upper Plenum Test Facility) and APR1400 (Advanced Power Reactor 1400) geometries are studied to fill in the lack of knowledge about the phenomena that could occur in the DVI (Direct Vessel Injection) system downcomer. The experiments for the direct ECC bypass have been conducted in the transparent downcomer models of the UPTF and APR1400 using air and water. The flow patterns and the bypass mechanisms of the ECC bypass were identified and the characteristics of it in both downcomers were compared with each other. Based on the visual observations, the cross flow between the downward liquid film and circumferential gas was found to be the most important flow pattern of the bypass phenomena. An analysis for the flow regime was conducted and the Wallis parameters were introduced as the significant non-dimensional parameters of the multidimensional two-phase flow phenomena.

show abstract

Reactor safety issues resolved by the 2D/3D Program. International Agreement Report

Cited by 28 publications

References 0 publications

Assessment of TRACE CCFL Model with SBLOCA Experiment of IIST Facility

Assessment of TRACE CCFL Model with SBLOCA Experiment of IIST Facility

Droplet de-entrainment by inertial impaction on vertical rods in an air-droplet mixture flow

Experimental Study for Multidimensional ECC Behaviors in Downcomer Ann with Direct Vessel Injection Mode during the LBLOCA Reflood Phase

Contact Info

Product

Resources

About