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Once-Through Steam Generator (OTSG) with smaller size and larger heat transfer capability, is typically used for Small and Medium sized Reactors (SMRs).
The designers of innovative small and medium sized reactors pursue new design and deployment strategies making use of certain advantages provided by smaller reactor size and capacity to achieve reduced design complexity and simplified operation and maintenance requirements, and to provide for incremental capacity increase through multi-module plant clustering.
However, it may be difficult or impossible to incorporate passive systems extensively in large size reactors, but could be well fit into small and medium sized reactors.
Passive safety is a primary motive behind the development of small and medium sized reactors of various coolants.
Small and medium sized reactors without on site refueling have market in developing countries due to factory fabrication and easy transportation.
Interest in nuclear desalination is driven by the expanding global demand for fresh water, by concern about GHG emissions and pollutions from fossil fuels and in developments in small and medium sized reactors that might be more suitable than large power reactors.
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The Soluble Boron Free (SBF) and Burnable Poison Free (BPF) concepts are more viable in small and medium size reactors (SMRs) because it makes the plant simpler and uniform burnup can also be achieved throughout the core life.
A High Temperature Gas-cooled Reactor (HTGR) system was generally designed and planned to be constructed in a medium size reactor (around 600 MWe power output) in the past.
As successful as traditional nuclear propulsion has been in the naval and ice breaker ship segments, one aspect of the industry that escaped attention in the commercial sector is the use of modern small and medium size reactor technology on-board ocean going vessels.
The node wise macroscopic cross-sections for each nominal and off-nominal of a typical medium sized PWR reactor core conditions which are calculated by WIMS-D5 and CITATION codes are tabulated in this system and can be retrieved by structured query language extremely rapid on demand.
A comparative study has been made on the mechanical energy released in a core disruptive accident resulting from an unprotected loss of flow accident (LOFA) in a medium sized liquid metal fast breeder reactor with oxide, carbide and metal fuels.
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