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Design and Analysis of Sodium-cooled Fast Reactor Systems for Nuclear Waste Minimization

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개인저자Lin, Ching-Sheng.
단체저자명Purdue University. Nuclear Engineering.
서명/저자사항Design and Analysis of Sodium-cooled Fast Reactor Systems for Nuclear Waste Minimization.
발행사항[S.l.] : Purdue University., 2018
발행사항Ann Arbor : ProQuest Dissertations & Theses, 2018
형태사항149 p.
소장본 주기School code: 0183.
ISBN9780438018914
일반주기 Source: Dissertation Abstracts International, Volume: 79-10(E), Section: B.
Adviser: Won Sik Yang.
요약The primary objective of this study was to develop fuel cycle options that minimize the nuclear waste generation using sodium-cooled fast reactor systems. In addition, this study aims to develop a new method that improves the accuracy in analyzi
요약Two "two-stage" fast spectrum fuel cycle options (Options 1 and 2) were proposed. The first option is a two-stage fuel cycle option of continuous recycle of Pu in sodium-cooled fast reactor (SFR) and subsequent burning of minor actinides (MAs) i
요약For the fuel cycle Option 2, the less energetic neutrons in the moderated target assembly enhance the transmutation performance. It is found that the use of moderated target assemblies in SFR reduces the number of required second-stage ADS by a
요약The verification test result suggests that VAREPD calculation can accurately retrieve the nuclide density distribution inside the moderated target assembly. The root-mean-square (RMS) error in the nuclide densities at the end of cycle is 5.5% fo
요약In summary, analysis results showed that all three proposed fuel cycle options could achieve high reduction in the nuclear waste generation because of the continuous recycle of the Pu and MAs. The SFR in the Options 1 and 2 may have a potential
일반주제명Nuclear engineering.
언어영어
기본자료 저록Dissertation Abstracts International79-10B(E).
Dissertation Abstract International
대출바로가기http://www.riss.kr/pdu/ddodLink.do?id=T14997933

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