Detailed Analysis of Late-Phase Core-Melt Progression for the Evaluation of In-Vessel Corium Retention

Park, R. J.; Kim, S. B.; Suh, Kune Y.; Rempe, Joy L.; Cheung, F. B.

doi:10.13182/nt06-a3790

Cited by 12 publications

(5 citation statements)

References 3 publications

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“…A steady state calculation was performed to verify the input nodalization of SCDAP/RELAP5/MOD3.3. The steady state results of the SCDAP/RELAP5/MOD3.3 calculation for a selected set of parameters were in very good agreement with the APR1400 operating conditions (Park et al, 2006). The steady state conditions obtained from the simulation are used as initial conditions for the transient calculation.…”

Section: Sbloca Sequence Analysis Using Scdap/relap5mentioning

confidence: 59%

Evaluation of corium behavior in the lower plenum of the reactor vessel during a severe accident

Park

Kang

Kim

2015

Nuclear Engineering and Design

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Section: Sbloca Sequence Analysis Using Scdap/relap5mentioning

confidence: 59%

Evaluation of corium behavior in the lower plenum of the reactor vessel during a severe accident

Park

Kang

Kim

2015

Nuclear Engineering and Design

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“…In order to investigate the effects of various SAMG entry conditions, three cases of initiating events are selected: SBLOCA, SBO, and TLOFW. Table 3 shows initiating events that have a high probability of transition to a severe accident based on the PSA Level 1 analysis [21]. For the SBLOCA, a 1.35-inch break on a cold leg is assumed, and loss of all offsite power and all secondary feed water are assumed for the SBO and TLOFW, respectively.…”

Section: Simulation Descriptions 21 Melcor Description and Input Momentioning

confidence: 99%

“…Therefore, this study focuses on the analysis of the effects of the CET as the SAMG entry condition on the effectiveness of severe accident management of Korean OPR1000 using the severe accident analysis code MELCOR 1.8.6. Given the important accident scenarios based on PSA Level 1 analysis, major accident scenarios could be selected to include SBLOCA, SBO, and TLOFW [21]. Using these scenarios, the important objectives of this study are first to investigate the application of mitigation strategy at various SAMG entry conditions for postulated accident scenarios in view of reactor pressure vessel (RPV) failure and to analyze the effectiveness and adverse effects of the mitigation strategies.…”

Section: Introductionmentioning

confidence: 99%

Effectiveness and adverse effects of reactor coolant system depressurization strategy with various severe accident management guidance entry conditions for OPR1000

Seo

Lee

et al. 2014

Journal of Nuclear Science and Technology

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Severe accident analysis for Korean OPR1000 with MELCOR 1.8.6 was performed by adapting a mitigation strategy under different entry conditions of Severe Accident Management Guidance (SAMG). The analysis was focused on the effectiveness of the mitigation strategy and its adverse effects. Four core exit temperatures (CETs) were selected as SAMG entry conditions, and Small Break Loss of Coolant Accident (SBLOCA), Station Blackout (SBO), and Total Loss of Feed Water (TLOFW) were selected as postulated scenarios that may propagate into severe accidents. In order to delay reactor pressure vessel (RPV) failure, entering the SAMG when the CET reached 923 K, 923 K, and 753 K resulted in the best results for SBLOCA, SBO, and TLOFW scenarios, respectively. This implies that using event-based diagnosis for severe accidents may be more beneficial than using symptom-based diagnosis. There is no significant difference among selected SAMG entry conditions in light of the operator's available action time before the RPV failure. Potential vulnerability of the RPV due to hydrogen generation was analyzed to investigate the foreseeable adverse effects that act against the accident mitigation strategies. For the SBLOCA cases, mitigation cases generated more hydrogen than the base case. However, the amount of hydrogen generated was similar between the base and mitigation cases for SBO and TLOFW. Hydrogen concentrations of containment were less than 5% before RPV failure for most cases.

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“…The initial melt pool conditions, such as melt mass, melt pool temperature and so on, were determined by using the SCDAP/RELAP5 computer code [21] for two severe accident sequences of the APR1400 at KAERI(Korea Atomic Energy Research Institute) [22]. In this analysis, TLFW(Total Loss of Feed Water) and SBLOCA(Small Break Loss of Coolant Accident) without SI(Safety Injection) were selected as the main severe accident sequences, which come from the level 1 PSA(Probabilistic Safety Assessment) results for the APR1400.…”

Section: Melt Pool Configuration In the Apr1400mentioning

confidence: 99%

Corium Behavior in the Lower Plenum of the Reactor Vessel Under Ivr-Ervc Condition: Technical Issues

Park¹,

Kang²,

Hong³

et al. 2012

Nuclear Engineering and Technology

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Detailed Analysis of Late-Phase Core-Melt Progression for the Evaluation of In-Vessel Corium Retention

Cited by 12 publications

References 3 publications

Evaluation of corium behavior in the lower plenum of the reactor vessel during a severe accident

Evaluation of corium behavior in the lower plenum of the reactor vessel during a severe accident

Effectiveness and adverse effects of reactor coolant system depressurization strategy with various severe accident management guidance entry conditions for OPR1000

Corium Behavior in the Lower Plenum of the Reactor Vessel Under Ivr-Ervc Condition: Technical Issues

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