Results 1 to 10 of about 69,304 (159)

High-Temperature Characterization of Melted Nuclear Core Materials: Investigating Corium Properties Through the Case Studies of In-Vessel and Ex-Vessel Retention

open access: yesFrontiers in Energy Research, 2022
During a severe accident in a nuclear reactor, the molten core—or corium—may be relocated into the reactor vessel’s lower plenum in case of core support plate failure.
Jules Delacroix   +2 more
doaj   +3 more sources

Uncertainty analysis of molten corium In-Vessel Retention under External Reactor Vessel Cooling

open access: yesInternational Journal of Advanced Nuclear Reactor Design and Technology, 2023
External Reactor Vessel Cooling (ERVC) is a key measure to realize molten corium In-Vessel Retention (IVR). The uncertainty of severe accident in core leads to the uncertainty of molten pool parameters in lower head, which may threat the reliability of ...
Shihao Wu   +6 more
doaj   +2 more sources

Evaluation of heat-flux distribution at the inner and outer reactor vessel walls under the in-vessel retention through external reactor vessel cooling condition

open access: yesNuclear Engineering and Technology, 2015
Background: A numerical simulation was carried out to investigate the difference between internal and external heat-flux distributions at the reactor vessel wall under in-vessel retention through external reactor vessel cooling (IVR-ERVC). Methods: Total
Jaehoon Jung   +3 more
doaj   +3 more sources

In-Vessel Melt Retention of Pressurized Water Reactors: Historical Review and Future Research Needs

open access: yesEngineering, 2016
A historical review of in-vessel melt retention (IVR) is given, which is a severe accident mitigation measure extensively applied in Generation III pressurized water reactors (PWRs).
Weimin Ma, Yidan Yuan, Bal Raj Sehgal
doaj   +3 more sources

Influence of an in-vessel debris bed on the heat load to a reactor vessel under an IVR condition

open access: yesNuclear Engineering and Technology, 2023
We measured the heat load to a reactor vessel with and without the in-vessel debris bed under an IVR-ERVC condition. Mass transfer methodology was adopted based on heat and mass transfer analogy to achieve high Ra′H of order ∼1015 with compact test rigs.
Joon-Soo Park   +2 more
doaj   +1 more source

Test of Critical Heat Flux on Outer Surface of CAP1400 Pressurized Reactor Vessel

open access: yesShanghai Jiaotong Daxue xuebao, 2022
A full height sliced test facility is established based on the modeling process. The heating test section is manufactured by adopting the explosive welding technology, and the surface of carbon steel can simulate the actual surface characteristic of a ...
SHI Guobao, ZHENG Mingguang, ZHANG Kun, KUANG Bo, LIU Pengfei
doaj   +1 more source

Development of thermal creep model for reactor pressure vessel lower head and application in OLHF experimental analysis

open access: yesHe jishu, 2022
BackgroundIn the event of a reactor severe accident, in-vessel retention (IVR) is a very effective and important severe accident mitigation measure. The lower head of the reactor pressure vessel (RPV) plays an important role in IVR strategy.
YANG Hao   +4 more
doaj   +1 more source

Study on the Calculation Method of Molten Pool Decay Heat Distribution under IVR Condition

open access: yesFrontiers in Energy Research, 2021
As an important strategy to mitigate severe accidents, the in-vessel retention (IVR) technique has been applied to the new generation of pressurized water reactor (PWR).
Yisheng Hao   +11 more
doaj   +1 more source

Analysis of heat transfer of the RPV lower head under severe accidents with ASTEC

open access: yesHe jishu, 2023
BackgroundAmong the mitigating strategies for severe accidents, the in-vessel retention (IVR) is one of the useful remission measurements. The key point to evaluating IVR is to analyze that the final steady-state thermal load of the melt does not exceed ...
ZUO Jiaxu   +4 more
doaj   +1 more source

Study on Thermal Shock Failure Characteristics of RPV During IVR System Start-Up for Typical Advanced PWR

open access: yesFrontiers in Energy Research, 2022
When the large pressurized water reactor in-vessel retention (IVR) system is put into operation, the outer wall of the reactor pressure vessel (RPV) will experience severe temperature fluctuations and be subjected to high internal pressure loads at the ...
Dahuan Zhu   +6 more
doaj   +1 more source

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