Coupled neutronic/thermal-hydraulic hot channel analysis of high power density civil marine SMR cores

被引:23
作者
Alam, Syed Bahauddin [1 ]
de Oliveira, Rodrigo G. G. [2 ]
Goodwin, Cameron S. [3 ]
Parks, Geoffrey T. [1 ]
机构
[1] Univ Cambridge, Dept Engn, Cambridge CB2 1PZ, England
[2] Paul Scherrer Inst, PSI Aarebrucke, CH-5232 Villigen, Switzerland
[3] Rhode Isl Nucl Sci Ctr, 16 Reactor Rd, Narragansett, RI 02882 USA
关键词
Civil marine propulsion; Small modular reactor; Soluble-boron-free operation; Micro-heterogeneous thorium-based duplex fuel; Neutronic/thermal-hydraulic coupling; Hybrid Monte Carlo; Sub-channel analysis; High power density SMR; THORIA-URANIA FUELS; NUCLEAR PROPULSION; REACTOR; DESIGN; FEASIBILITY; SHIPS; IRIS;
D O I
10.1016/j.anucene.2018.12.031
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Core average power density of standard small modular reactors (SMR) are generally limited to 60-65 MW/m(3), which is 40% lower than for a standard civil PWR in order to accommodate better thermal margins. While designing a SMR core for civil marine propulsion systems, it is required to increase its power density to make more attractive for future deployment. However, there are obvious thermal-hydraulic (TH) concerns regarding a high power density (HPD) core, which needs to be satisfied in order to ensure safe operation through accurate prediction of the TH parameters. This paper presents a coupled neutronic/thermal-hydraulic (TH) hot channel analysis of a HPD 375 MWth soluble-boron-free PWR core using 19.25% U-235 enriched micro-heterogeneous ThO2-UO2 duplex fuel and 16% U-235 enriched homogeneously mixed all-UO2 fuel with a 15 effective full-power-years (EFPY) core life. To perform this analysis the hybrid Monte Carlo reactor physics code MONK is coupled with sub-channel analysis TH code COBRA-EN. This approach is used to investigate the feasibility of different HPD marine PWR concepts and to identify the main TH challenges characterising these designs. To design HPD cores of between 82 and 111 MW/m(3), three cases were chosen by optimizing the fuel pin diameter, pin pitch and pitch-to-diameter ratio. These cases have been studied to determine whether TH safety limits are satisfied by evaluating key parameters, such as minimum departure from nucleate boiling ratio, surface heat flux, critical heat flux, cladding inner surface and fuel centreline temperatures, and pressure drop. The results show that it is possible to achieve a core power density of 100 MW/m(3) for both the candidate fuels, a similar to 50% improvement on the reference design (63 MW/m(3)), while meeting the target core lifetime of 15 EFPY and remaining within TH limits. The size of the pressure vessel can therefore be reduced substantially and the economic competitiveness of the proposed civil marine PWR reactor core significantly improved. (C) 2018 Elsevier Ltd. All rights reserved.
引用
收藏
页码:400 / 411
页数:12
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