Improvement of Molten Core Cooling Strategy in a Severe Accident Management Guideline

Song, J. H.; Huh, Changwook; Suh, Namduk

doi:10.13182/nt12-a13592

Cited by 4 publications

(2 citation statements)

References 9 publications

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“…So a recent severe accident study using MELCOR by Song et al [11] utilized the almost identical nodalization to the current plant nodalization. Rather, the nodalization used in the current study has been improved in terms of dedicated upper plenum (CV190) for simulating the appropriate CET.…”

Section: Features and Melcor Input Mode Of Opr1000mentioning

confidence: 99%

“…Also cavity flooding strategy of SAMG was closely analyzed through comparison of lower head CHF correlation using MELCOR [10]. Severe accident mitigation strategies such as RCS depressurization and external reactor vessel cooling were assessed for postulated SBO using MELCOR [11]. As such, several severe accident scenarios have been analyzed using the state-of-the-art severe accident codes.…”

Section: Introductionmentioning

confidence: 99%

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Validation of RCS depressurization strategy and core coolability map for independent scenarios of SBLOCA, SBO, and TLOFW

Lee

Kim

et al. 2013

Journal of Nuclear Science and Technology

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Severe accident analysis for Small Break (SB), Middle Break (MB), and Large Break (LB) Loss-Of-Coolant Accident (LOCA), Station Black Out (SBO), Total Loss-Of-Feed-Water (TLOFW) was performed and effectiveness of Reactor Coolant System (RCS) depressurization strategies of OPR1000 was analyzed using MELCOR 1.8.6 code. Required injection flow rate has been derived using Core Exit Temperature (CET) information obtained from MELCOR calculation and a simple model and corresponding coolability map have been suggested to assist effective operator action. The depressurization strategies using secondary Atmospheric Dump Valve (ADV) for SBLOCA, pressurizer Safety Depressurization System (SDS) for SBO and TLOFW were introduced in 5 min since the initiation of Severe Accident Management Guidance (SAMG). Respective mitigation strategy employed leads to significant delay of the reactor pressure vessel failure and RCS pressure at Reactor Pressure Vessel (RPV) failure was lower than the SAMG target pressure of 2.86 MPa. Thus, possibility of High Pressure Melt Ejection (HPME) and impair of containment building is expected to avoid effectively. Using CET information obtained from MELCOR calculation, a simple model and a coolability map for the required injection flow rate were developed for recovery of core coolability. It is suggested that the coolability map based on MELCOR calculation results may provide decisive and intuitive information to operators for more effective safety management.

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Section: Features and Melcor Input Mode Of Opr1000mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%