Safeguardability assessment for the new HALEU fuel fabrication facility고순도 저농축우라늄 핵연료 성형가공시설에 대한 안전조치성 평가

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The nuclear industry is developing next-generation reactors to enhance energy security and address climate change. In the future, advanced reactors such as Small Modular Reactors (SMRs) are expected to utilize High Assay Low Enriched Uranium (HALEU) fuel, which typically has uranium-235 enrichment levels ranging from 5% to 20%. Consequently, the introduction of new fuel fabrication facilities is required to produce this new type of nuclear fuel for advanced reactors. From a nuclear safeguards perspective, the introduction of new nuclear facilities may raise unforeseen safeguards concerns such as dedicated misuse and sabotage. Moreover, applying existing safeguards regulations and surveillance systems directly to these facilities could pose several risks. This thesis evaluates the safeguards of a hypothetical fuel fabrication facility producing high assay low enriched uranium fuel, applying qualitative and quantitative methodologies.
Advisors
임만성researcher
Description
한국과학기술원 :원자력및양자공학과,
Publisher
한국과학기술원
Issue Date
2024
Identifier
325007
Language
eng
Description

학위논문(석사) - 한국과학기술원 : 원자력및양자공학과, 2024.8,[iii, 55 p. :]

Keywords

Safeguardability▼aFSA▼aMarkov▼aHALEU; Fuel fabrication; 안전조치성▼aFSA▼a마르코프▼aHALEU▼a핵연료 성형가공시설

URI
http://hdl.handle.net/10203/333000
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=1110123&flag=dissertation
Appears in Collection
NE-Theses_Master(석사논문)
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