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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2018.1
- 수록면
- 356 - 367 (12page)
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초록· 키워드
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A series of tests dedicated to station blackout (SBO) accident scenarios have been recently performed at thePrim€arkreislauf-Versuchsanlage (primary coolant loop test facility; PKL) facility in the framework of theOECD/NEAPKL-3 project. These investigations address current safety issues related to beyond design basis accidenttransients with significant core heat up. This work presents a detailed analysis using the best estimatethermalehydraulic code TRACE (v5.0 Patch4) of different SBO scenarios conducted at the PKL facility; failuresof high- and low-pressure safety injection systems together with steam generator (SG) feedwatersupply are considered, thus calling for adequate accidentmanagement actions and timelyimplementation ofalternative emergency cooling procedures to prevent core meltdown. The presented analysis evaluates thecapability of the applied TRACE model of the PKL facility to correctly capture the sequences of events in thedifferent SBO scenarios, namely the SBO tests H2.1, H2.2 run 1 and H2.2 run 2, including symmetric orasymmetric secondary side depressurization, primary side depressurization, accumulator (ACC) injection inthe cold legs and secondary side feeding with mobile pump and/or primary side emergency core coolantinjection from the fuel pool cooling pump. This study is focused specifically on the prediction of the core exittemperature, which drives the execution of the most relevant accident management actions. This workpresents, in particular, the key improvements made to the TRACE model that helped to improve the codepredictions, including the modeling of dynamical heat losses, the nodalization of SGs' heat exchanger tubesand theACCs. Another relevant aspect of thiswork is to evaluate howwell themodel simulations of the threedifferent scenarios qualitatively and quantitatively capture the trends and results exhibited by the actualexperiments. For instance, howthenumber of SGs considered for secondary side depressurization affects theheat transfer from primary side; how the discharge capacity of the pressurizer relief valve affects the dynamicsof the transient; how ACC initial pressure and nitrogen release affect the grace time between ACCinjection and subsequent core heat up; and howwell the alternative feeding modes of the secondary and/orprimary side with mobile injection pumps affect core quenching and ensure stable long-term core coolingunder controlled boiling conditions.
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참고문헌 (21)
참고문헌 신청
I. Toth / 2010 / Core exit temperature (CET) effectiveness in accident management of nuclear power reactors;Committee on the Safety of Nuclear Installations
J. Freixa / 2015 / Modelling guidelines for core exit temperature simulations with system codes / Nuclear Eng. Design 286:116~129
Division of Risk Assessment / 2013 / Office of Nuclear Regulatory Research, TRACE V5.840 Theory Manual - Field Equations, Solution Methods, and Physical Models
Paul Scherrer Institute / 2011 / Steady-state and Transient Analysis Research of the Swiss Reactors (STARS Project)
K. Umminger / 2012 / Integral test facility PKL: experimental PWR accident investigation / Sci. Technol. Nuclear Install. 2012
J. Freixa / 2015 / Modelling guidelines for core exit temperature simulations with system codes / Nuclear Eng. Design 286:116~129
Division of Risk Assessment / 2013 / Office of Nuclear Regulatory Research, TRACE V5.840 Theory Manual - Field Equations, Solution Methods, and Physical Models
Paul Scherrer Institute / 2011 / Steady-state and Transient Analysis Research of the Swiss Reactors (STARS Project)
K. Umminger / 2012 / Integral test facility PKL: experimental PWR accident investigation / Sci. Technol. Nuclear Install. 2012
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