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From the accident at the Japanese Fukusima NPP, an extreme event beyond the design basis is realized to be possible.
The systems of interest include existing or proposed systems that operate, for example, normal operation, in design basis accident conditions, and in severe accident scenario beyond the design basis.
Each [reactor will be examined for] robustness in the conditions which are beyond the design basis.
Lava flows are considered to be beyond the design basis of nuclear facilities, meaning that the potential for the occurrence of lava flows above some level of acceptable likelihood would exclude the site from development of nuclear facilities because safe control or shutdown of the facility under circumstances of lava flow inundation cannot be assured (IAEA 2011).
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The AB1600 safety system design employs a hybrid safety system, which consists of both active and passive systems for the design basis and the beyond-design basis accidents, to enhance the safety of the plant.
Vulnerability assessment of Structures Systems and Components (SSCs) of nuclear facilities for earthquake ground motion exceeding the design basis ground motion has become a key issue to ensure safety in case of highly improbable but possible extreme earthquake event beyond design basis.
Instead of the conservative bounding analysis methodology, a best-estimate analysis methodology has been developed and utilized since the design basis events accompanied by CMF in the digital PPS are categorized as beyond design bases events.
Given postulated accidents that go beyond the plant design basis, long term passive cooling for the nuclear reactor spent fuel pool is important to demonstrate.
It can be concluded that, due to the performed analyses and the implemented protection measures, main steam line and main feedwater line breaks at the postulated break locations will not lead to consequential failures beyond the defined design basis for accident mitigation.
Through these assumptions, we consider the response of the plant to multiple failures and therefore we extend our analysis beyond the normal "design basis".
Potential sodium discharge in the containment during postulated Beyond Design Basis Accidents (BDBAs) in Sodium-cooled Fast Reactors (SFRs) would have major consequences for accident development in terms of energetics and source term.
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