Investigation of critical safety function “Heat sink” at low power and cold condition for Kozloduy Nuclear Power Plant WWER-1000/V320

Andreeva, M.; Pavlova, M.P.; Groudev, Pavlin

doi:10.1016/j.anucene.2011.10.012

Cited by 11 publications

(1 citation statement)

References 2 publications

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“…All of the VVER series are 4loop PWRs with one horizontal steam generator on each loop. The VVER-1000/V320 removes the core decay heat after the LOOP event using the steam generators with the feedwater supplied from auxiliary and emergency feedwater systems [15]. The feedwater is pumped by motor-driven pumps from deaerator tank and storage tank with capacity of several days.…”

Section: Measures To Mitigate the Loss Of Offsite Power (Loop)mentioning

confidence: 99%

Preliminary Assessment of Engineered Safety Features Against Station Blackout in Selected PWR Models

Ekariansyah

Widodo²,

Susyadi³

et al. 2021

Tri Dasa Mega

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The 2011 Fukushima accident did not prevent countries to construct new nuclear power plants (NPPs) as part of the electricity generation system. Based on the IAEA database, there are a total of 44 units of PWR type NPPs whose constructions are started after 2011. To assess the technology of engineered safety features (ESFs) of the newly constructed PWRs, a study has been conducted as described in this paper, especially in facing the station blackout (SBO) event. It is expected from this study that there are a number of PWR models that can be considered to be constructed in Indonesia from the year of 2020. The scope of the study is PWRs with a limited capacity from 900 to 1100 MWe constructed and operated after 2011 and small-modular type of reactors (SMRs) with the status of at least under licensing. Based on the ESFs design assessment, the passive core decay heat removal has been applied in the most PWR models, which is typically using steam condensing inside heat exchanger within a water tank or by air cooling. From the selected PWR models, the CPR-1000, HPR-1000, AP-1000, and VVER-1000, 1200, 1300 series have the capability to remove the core decay heat passively. The most innovative passive RHR of AP-1000 and the longest passive RHR time period using air cooling in several VVER models are preferred. From the selected SMR designs, the NuScale design and RITM-200 possess more advantages compared to the ACP-100, CAREM-25, and SMART. NuScale represents the model with full-power natural circulation and RITM-200 with forced circulation. NuScale has the longest time period for passive RHR as claimed by the vendor, however the design is still under licensing process. The RITM-200 reactor has a combination of passive air and water-cooling of the heat exchanger and is already under construction.

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Section: Measures To Mitigate the Loss Of Offsite Power (Loop)mentioning

confidence: 99%