Show simple item record

dc.rights.licenseRestricted to current Rensselaer faculty, staff and students. Access inquiries may be directed to the Rensselaer Libraries.
dc.contributorJi, Wei
dc.contributorLiu, Li (Emily)
dc.contributorLian, Jie
dc.contributor.authorEvans, Beren Richard
dc.date.accessioned2021-11-03T08:48:54Z
dc.date.available2021-11-03T08:48:54Z
dc.date.created2017-07-03T14:13:55Z
dc.date.issued2017-05
dc.identifier.urihttps://hdl.handle.net/20.500.13015/1958
dc.descriptionMay 2017
dc.descriptionSchool of Engineering
dc.description.abstractShielding performance and secondary radiation data suggested that tungsten boron carbide was the most effective composite material. An analysis of the macroscopic cross-section contributions from constituent materials and interaction mechanisms was then performed in an attempt to determine the reasons for tungsten boron carbide’s success over the other investigated materials.
dc.description.abstractThese findings suggest that the inclusion of materials featuring high thermal absorption properties is more critical to composite neutron shield performance than the presence of constituent materials more inclined to maximize elastic scattering energy loss.
dc.description.abstractThis analysis determined that there was a positive correlation between a non-elastic interaction contribution towards a material’s total cross-section and shielding performance within the thermal and epi-thermal energy regimes. This finding was assumed to be a result of the boron-10 absorption reaction. The analysis also determined that within the faster energy regions, materials featuring higher non-elastic interaction contributions were comparable to those exhibiting primarily elastic scattering via low Z elements. This allowed for the conclusion that composite shield success within higher energy neutron spectra does not necessitate the use elastic scattering via low Z elements.
dc.description.abstractThis work details an investigation into the contributing factors behind the success of newly developed composite neutron shield materials. Monte Carlo simulation methods were utilized to assess the neutron shielding capabilities and secondary radiation production characteristics of aluminum boron carbide, tungsten boron carbide, bismuth borosilicate glass, and Metathene within various neutron energy spectra.
dc.language.isoENG
dc.publisherRensselaer Polytechnic Institute, Troy, NY
dc.relation.ispartofRensselaer Theses and Dissertations Online Collection
dc.subjectNuclear engineering
dc.titleEvaluation of shielding performance for newly developed composite materials
dc.typeElectronic thesis
dc.typeThesis
dc.digitool.pid178225
dc.digitool.pid178226
dc.digitool.pid178227
dc.rights.holderThis electronic version is a licensed copy owned by Rensselaer Polytechnic Institute, Troy, NY. Copyright of original work retained by author.
dc.description.degreeMS
dc.relation.departmentDept. of Mechanical, Aerospace, and Nuclear Engineering


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record