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An innovative core design for a soluble-boron-free small pressurized water reactor

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dc.citedby6
dc.contributor.authorYahya M.-S.en_US
dc.contributor.authorKim Y.en_US
dc.contributor.authorid56287449000en_US
dc.contributor.authorid57196440838en_US
dc.date.accessioned2023-05-29T06:57:09Z
dc.date.available2023-05-29T06:57:09Z
dc.date.issued2018
dc.descriptionControl rods; Monte Carlo methods; Small nuclear reactors; Stainless steel; BigT; Burnable absorber; Burnup reactivity swing; Control rod patterns; Nuclear data library; Radial power distributions; Radial power profile; Small modular reactors; Pressurized water reactorsen_US
dc.description.abstractThis research investigates the neutronic feasibility of a high-performance soluble-boron-free (SBF) small modular reactor (SMR) core based on a new burnable absorber concept called the �Burnable Absorber-Integrated Guide Thimble� (BigT). Three unique BigT designs were loaded into the core; each BigT design was judiciously ascertained from the core radial power profile to tailor the required reactivity depletion patterns for an SBF operation. The approach is demonstrated to work well as the SBF SMR design exceeds the targeted cycle length while successfully controlling its burnup reactivity swing between 634 and 800�pcm throughout most of its operation. This paper also describes the use of hafnium-doped stainless steel as mechanical shim (MS) rods to attain the core criticality. Because the worth of the MS rods is relatively small, insertion and withdrawal of the rods during operation hardly alter the core radial power distributions. The resulting axial power profile, meanwhile, displays a more refined bottom-skewed pattern during the early portion of the irradiation cycle due to partial top-half insertion of the MS rods. This investigation further deliberates on a modified checker board control rod pattern to assure safe cold shutdown of the core. All calculations in this multiphysics assessment of the 3D SBF SMR core were completed by using a 2-step Monte Carlo deterministic hybrid procedure based on the Monte Carlo Serpent and COREDAX diffusion codes with the ENDF/B-7.1 nuclear data library. Copyright � 2017 John Wiley & Sons, Ltd.en_US
dc.description.natureFinalen_US
dc.identifier.doi10.1002/er.3792
dc.identifier.epage81
dc.identifier.issue1
dc.identifier.scopus2-s2.0-85038599595
dc.identifier.spage73
dc.identifier.urihttps://www.scopus.com/inward/record.uri?eid=2-s2.0-85038599595&doi=10.1002%2fer.3792&partnerID=40&md5=562a42e15fa70a977f39bb23853c7e54
dc.identifier.urihttps://irepository.uniten.edu.my/handle/123456789/24225
dc.identifier.volume42
dc.publisherJohn Wiley and Sons Ltden_US
dc.relation.ispartofAll Open Access, Bronze
dc.sourceScopus
dc.sourcetitleInternational Journal of Energy Research
dc.titleAn innovative core design for a soluble-boron-free small pressurized water reactoren_US
dc.typeConference Paperen_US
dspace.entity.typePublication
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