Experiments on in-vessel melt coolability in the EC-FOREVER Program

Sehgal, Bal Raj; Giri, Asis; Chikkanagoudar, U.; Karbojian, Aram

doi:10.1016/j.nucengdes.2006.03.056

Cited by 21 publications

(4 citation statements)

References 11 publications

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“…Limitations to top cooling options have also been addressed by the investigations in the frame of the FOREVER experiment, reported in the contribution of Sehgal et al (2006) in Part 4. This contribution addresses in-vessel coolability and specifically gap cooling.…”

Section: Coolabilitymentioning

confidence: 99%

Considerations on ex-vessel corium behavior: Scenarios, MCCI and coolability

Allelein

Bürger

2006

Nuclear Engineering and Design

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Section: Coolabilitymentioning

confidence: 99%

Considerations on ex-vessel corium behavior: Scenarios, MCCI and coolability

Allelein

Bürger

2006

Nuclear Engineering and Design

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“…However, the TMI-2 data only represent information from one type of accident and reactor design. Although several tests [38][39][40] were completed with full scale penetrations, there are questions related to test geometry and the use of simulant melts. The 1/5th -scale tests completed at SNL [41,42] provide the most detailed data for benchmarking vessel creep rupture.…”

Section: Introductionmentioning

confidence: 99%

Reactor Safety Gap Evaluation of Accident-Tolerant Components and Severe Accident Analysis

Farmer

Bunt²,

Corradini

et al. 2016

Nuclear Science and Engineering

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The overall objective of this study was to conduct a technology gap evaluation on accident tolerant components and severe accident analysis methodologies with the goal of identifying any data and/or knowledge gaps that may exist, given the current state of light water reactor (LWR) severe accident research, and additionally augmented by insights obtained from the Fukushima accident. The ultimate benefit of this activity is that the results can be used to refine the Department of Energy's (DOE) Reactor Safety Technology (RST) research and development (R&D) program plan to address key knowledge gaps in severe accident phenomena and analyses that affect reactor safety and that are not currently being addressed by the industry or the Nuclear Regulatory Commission (NRC).In the aftermath of the March 2011 accident at the Fukushima Daiichi nuclear power plant (Fukushima; see Figure 1), the nuclear community has been reassessing certain safety assumptions about nuclear reactor plant design, operations and emergency actions, particularly with respect to extreme events that might occur and that are beyond current design bases.

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“…Thus, severe accident management is practiced for new reactors and the existing plants are being retrofitted for melt coolability and stabilization so as to prevent and mitigate the causes for early containment failure and the containment bypass. The issue still remaining is that of accident stabilization and termination through the cooling of the core melt either in-vessel or ex-vessel (Sehgal, 2006;Sehgal et al, 2006). In the ex-vessel condition, the severe accidents are generally managed by a core catcher.…”

Section: Introductionmentioning

confidence: 99%