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Lee, Deokjung
Computational Reactor physics & Experiment lab (CORE Lab)
Research Interests
  • Reactor Analysis computer codes development
  • Methodology development of reactor physics
  • Nuclear reactor design(SM-SFR,PWR and MSR)

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Optimization study of Ultra-long Cycle Fast Reactor core concept

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Title
Optimization study of Ultra-long Cycle Fast Reactor core concept
Author
Tak, TaewooLee, DeokjungKim, T.K.Hong, Ser Gi
Issue Date
2014-11
Publisher
PERGAMON-ELSEVIER SCIENCE LTD
Citation
ANNALS OF NUCLEAR ENERGY, v.73, pp.145 - 161
Abstract
An optimization of an Ultra-long Cycle Fast Reactor (UCFR) design with a power rating of 1000 MW (electric), UCFR-1000, has been performed. Firstly, geometric optimization has been performed in the aspects of core size and core shape in terms of thermal-hydraulic (TH) feedback. Secondly, fuel composition optimization has been performed by adopting pressurized water reactor (PWR) spent fuel (SF) as a blanket material as well as natural uranium (NU). Thirdly, thorium has been loaded in the inner core for the optimization of radial power distribution. Lastly, a small-size UCFR with a power rate of 100 MWe has been developed with optimization of maximum neutron flux and fast neutron fluence limit for a short term deployable nuclear reactor. The equivalent diameter and the height of the optimized UCFR-1000 core are 5.9 and 2.4 m, respectively, while the equivalent diameter and the height of the optimized UCFR-100 core are 4.3 and 1.0 m, respectively. The size of the optimized UCFR-1000 has been enlarged in the radial direction and shortened in the axial direction from those of the initial UCFR design (Tak et al., 2013a) and this modification makes the burning speed of active core movement slower. It has been confirmed for both designs that a full-power operation of 60 years without refueling is feasible with respect to isotopics and criticality by a breed-and-burn strategy. The core performance characteristics of both designs have been evaluated in terms of axial/radial power shapes, neutron flux and nuclide distributions, breeding ratio, reactivity feedback coefficients, control rod worth, etc. By the design optimization study in this paper, the reductions of maximum neutron flux, fast neutron fluence, and axial/radial power peaking have been achieved, which are favorable for the safety of the UCFR.
URI
https://scholarworks.unist.ac.kr/handle/201301/5422
URL
http://www.scopus.com/inward/record.url?partnerID=HzOxMe3b&scp=84904288147
DOI
10.1016/j.anucene.2014.06.030
ISSN
0306-4549
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