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Coupled thermal-hydraulics and neutron-physics analysis of SCWR with mixed spectrum core
Authors:X.J. Liu  X. Cheng
Affiliation:1. School of Nuclear Science and Engineering, Shanghai Jiao Tong University, 800 Dong Chuan Road, Shanghai 200240, China;2. Institute of Fusion and Nuclear Technology, Karlsruhe Institute of Technology (KIT), Kaiserstr. 12, 76131 Karlsruhe, Germany;1. Shanghai Jiao Tong University, Shanghai, China;2. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, China;3. CAEP Software Centre for High Performance Numerical Simulation, Beijing, China;4. Nanjing University of Aeronautics and Astronautics, Jiangsu, China;1. State Key Laboratory of Multiphase Flow in Power Engineering, Department of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China;2. Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology-SKL-ANET, Xi’an Jiaotong University, Xi’an 710049, China;1. CanmetMATERIALS, Natural Resources Canada, 183 Longwood Rd. S., Hamilton, ON, Canada;2. VTT Technical Research Center of Finland, Materials for Power Engineering, P.O. Box 1000, FI-02044 VTT, Finland;3. AECL Chalk River Laboratory, Chalk River, Ontario, Canada
Abstract:The new SCWR conceptual design (SCWR-M) is proposed on the basis of a mixed spectrum core consisting of a thermal spectrum zone and a fast spectrum zone. This new core design is considered to be the hybrid of the existing thermal SCWR and fast SCWR cores. It combines the merits of both thermal and fast SCWR cores, at the same time minimizes their shortcomings. For the thermal zone, the difficulties in the mechanical design and the maximum cladding temperature can be reduced as far as possible by the co-current flow mode; and for the fast zone, a sufficiently large negative coolant void reactivity coefficient and breeding ratio can be achieved by the multi-layer arrangement of fuel rods.The performance, including the burn-up behavior, of the proposed core is investigated with 3-D coupled neutron-physical and thermal-hydraulic calculations. During the coupling procedure, the thermal-hydraulic behavior is analyzed using a sub-channel analysis code and the neutron-physical performance is computed with a 3-D diffusion code. The results obtained so far have shown that the mixed spectrum SCWR concept (SCWR-M) is feasible and promising.
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