자료유형 | 학위논문 |
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서명/저자사항 | Design and Analysis of Sodium-cooled Fast Reactor Systems for Nuclear Waste Minimization. |
개인저자 | Lin, Ching-Sheng. |
단체저자명 | Purdue University. Nuclear Engineering. |
발행사항 | [S.l.]: Purdue University., 2018. |
발행사항 | Ann Arbor: ProQuest Dissertations & Theses, 2018. |
형태사항 | 149 p. |
기본자료 저록 | Dissertation Abstracts International 79-10B(E). Dissertation Abstract International |
ISBN | 9780438018914 |
학위논문주기 | Thesis (Ph.D.)--Purdue University, 2018. |
일반주기 |
Source: Dissertation Abstracts International, Volume: 79-10(E), Section: B.
Adviser: Won Sik Yang. |
요약 | The 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 |
요약 | Two "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 |
요약 | For 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 |
요약 | The 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 |
요약 | In 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 |
일반주제명 | Nuclear engineering. |
언어 | 영어 |
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