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contributor authorSasaki, Ryotaro;Yamaji, Akifumi;Uchimura, Kyota
date accessioned2022-12-27T23:19:31Z
date available2022-12-27T23:19:31Z
date copyright6/15/2022 12:00:00 AM
date issued2022
identifier issn2332-8983
identifier otherners_009_02_021501.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4288382
description abstractThe small modular reactor (SMR) class core design concept of once-through supercritical light water-cooled reactor (SCWR) with fast neutron spectrum (super fast reactor (FR)) is being developed at Waseda University. For the 300 MWel class design, complete core meltdown may need to be considered in case of a severe accident. This study proposes the new in-vessel retention (IVR) concept of the SMR class super FR (super FR-IVR), which can avoid recriticality even if the whole core relocates to the lower plenum of the reactor pressure vessel (RPV). The core characteristics with a given set of design specifications and criteria are evaluated based on fully coupled neutronics and thermal-hydraulics core burnup calculations. The debris criticality is evaluated based on Monte Carlo based method to consider the RPV lower plenum and debris configurations. The relationships between the 300 MWel class core design with the inner vessel diameter of 2.32 m and the IVR design are revealed. By reducing the operation cycle length from 720 days to 360 days and increasing the core inlet temperature from 280 °C to 370 °C, the required IVR submergence level could be reduced from 2.18 m to 1.38 m, assuming that the debris bed (melt pool) is homogeneous. However, when fully stratified debris configurations are assumed, the required disperser height and the corresponding IVR submergence level may increase to about 2.70 m.
publisherThe American Society of Mechanical Engineers (ASME)
titleDesign Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention
typeJournal Paper
journal volume9
journal issue2
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4053827
journal fristpage21501
journal lastpage21501_7
page7
treeJournal of Nuclear Engineering and Radiation Science:;2022:;volume( 009 ):;issue: 002
contenttypeFulltext


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