CALPHAD analyses of molten chloride fast reactor fuels with U/Pu cyclesU/Pu 주기를 이용하는 염화물계 용융염 고속로 핵연료에 대한 CALPHAD 분석

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In this study, a comprehensive Calculation of Phase Diagrams (CALPHAD) approach was undertaken to assess the effects of molten chloride fast reactor (MCFR) fuel chemistry on the initial and transient performance of MCFR fuel systems that utilize U/Pu fuel cycles. In this context, thermodynamic optimization of constitutive binary and ternary subsystems of the NaCl, KCl, MgCl2, CaCl2, UCl3, PuCl3, RbCl, CsCl, SrCl2, and BaCl2 containing system was performed and subsequently used to derive the phase behavior of high-order constitutive mixtures. The simulation results indicate that the appropriate modification of base salt compositions can significantly augment the heat transfer and melting properties of MCFR fuels, consequently leading to enhanced fuel performances, better compatibility with structural materials, and improved reactor economics. Moreover, it was discovered that the response of the fuel properties to shifts in fuel chemistry largely depends on solid phase interactions between the base salt and actinide content. The novel insights from this study bring forth several practical applications in various key facets of molten salt reactor design, such as fuel composition optimization, periodic optimization of fuel cleanup schemes, and structural material integrity assurance.
Advisors
Ryu, Ho Jinresearcher류호진researcher
Description
한국과학기술원 :원자력및양자공학과,
Publisher
한국과학기술원
Issue Date
2023
Identifier
325007
Language
eng
Description

학위논문(석사) - 한국과학기술원 : 원자력및양자공학과, 2023.2,[v, 99 p. :]

Keywords

CALPHAD▼aMolten Salt Reactor▼aU/Pu Fuel Cycles▼aSoluble Fission Products▼aSoluble Fission Products▼aSolid Solutions▼aModified Quasichemical Model (MQM); 열역학 상평형도 계산법▼a용융염 원자로▼a염화물계 용융염 핵연료 성능▼a우라늄–플루토늄 주기▼a가용성 핵분열 생성물▼a고용체▼a수정된 준화학 모델

URI
http://hdl.handle.net/10203/309762
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=1032841&flag=dissertation
Appears in Collection
NE-Theses_Master(석사논문)
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