Evaluating direct vessel injection accident-event progression of AP1000 and key figures of merit to support the design and development of water-cooled small modular reactors

Abdellatif, Hossam H.; Bhowmik, Palash K.; Arcilesi, David; Sabharwall, Piyush

doi:10.1016/j.net.2024.01.049

Evaluating direct vessel injection accident-event progression of AP1000 and key figures of merit to support the design and development of water-cooled small modular reactors

Journal Article · Wed Feb 14 23:00:00 EST 2024 · Nuclear Engineering and Technology

DOI:https://doi.org/10.1016/j.net.2024.01.049· OSTI ID:2352617

Abdellatif, Hossam H. ^[1]; ^[2]; Arcilesi, David ^[1]; ^[2]

University of Idaho, Idaho Falls, ID (United States)
Idaho National Laboratory (INL), Idaho Falls, ID (United States)

The passive safety systems (PSSs) within water-cooled reactors are meticulously engineered to function autonomously, requiring no external power source or manual intervention. They depend exclusively on inherent natural forces and the fundamental principles of reactor physics, such as gravity, natural convection, and phase changes, to manage, alleviate, and avert the release of radioactive materials into the environment during accident scenarios like a loss-of-coolant accident (LOCA). PSSs are already integrated into such operating commercial reactors as the Advanced Pressurized Reactor-1000 MWe (AP1000) and the Water-Water Energetic Reactor-1200 MWe (WWER-1200) are adopted in most of the upcoming small modular reactor (SMR) designs. Examples of water-cooled SMR PSSs are the passive emergency core-cooling system (ECCS), passive containment cooling system (PCCS), and passive decay-heat removal system, the designs of which vary based on reactor system-design requirements. However, understanding the accident-event progression and phases of a LOCA is pivotal for adopting a specific PSS for a new SMR design. This study covers the accident-event progression for direct vessel injection (DVI) small-break loss-of-coolant accident (SB-LOCA), associated physics phenomena, knowledge gaps, and important figures of merit (FOMs) that may need to be evaluated and assessed to validate thermal-hydraulics models with an available experimental dataset to support new SMR design and development.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Science (SC)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 2352617

Report Number(s):: INL/JOU--23-73120-Revision-1

Journal Information:: Nuclear Engineering and Technology, Journal Name: Nuclear Engineering and Technology Journal Issue: 2024 Vol. 420; ISSN 1738-5733

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Evaluating direct vessel injection accident-event progression of AP1000 and key figures of merit to support the design and development of water-cooled small modular reactors

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