5-9 September 2016
Prague Congress Centre
Europe/Prague timezone

P1.162 Parameter study on helium cooled ceramic breeder blanket neutronics with CFETR system code

5 Sep 2016, 14:20
1h 40m
Foyer 2A (2nd floor), 3A (3rd floor) (Prague Congress Centre)

Foyer 2A (2nd floor), 3A (3rd floor)

Prague Congress Centre

5. května 65, Prague, Czech Republic
Board: 162
Poster H. Fuel Cycle and Breeding Blankets P1 Poster session

Speaker

Kun Xu (School of Nuclear Sciences and Technology)

Description

The development of system code for CFETR (China Fusion Engineering Test Reactor) is in progress for the optimization of the CFETR design in both core physics and engineering. As one of the key modules, the neutronics interface module has been implemented within the engineering framework of CFETR system code. The neutronics interface module, which is designed to work in conjunction with the general neutronics codes, is constituted by three sub-modules at present: the Tokamak fusion neutron source modeling sub-module, the neutronics modeling sub-module and the post processing sub-module. This work presents the parameter study on helium cooled ceramic breeder blanket neutronics with the neutronics interface module of the CFETR system code. The parameterized 3-D neutronic model of CFETR was set in the first place. Afterwards, the workflows of neutronic analyses were established. Several concerned geometric and material composition parameters of CFETR blanket were selected as arguments of certain ranges to pass the sensitivity analyses for target parameters (such as the tritium breeding ratio). And then, the workflows were abstracted as mathematical models and the so-called response surfaces for target parameters were established. Based on the workflow or the response surfaces, the fast estimation and optimization of target parameters could be achieved. Finally, an optimal set of parameters was proposed for CFETR helium cooled ceramic breeder blanket.

Co-authors

Kun Xu (School of Nuclear Sciences and Technology, University of Science and Technology of China, Hefei 230026, Anhui, China) Mingzhun Lei (Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, Anhui, China) Minyou Ye (School of Nuclear Sciences and Technology, University of Science and Technology of China, Hefei 230026, Anhui, China;Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, Anhui, China) Shenji Wang (School of Nuclear Sciences and Technology, University of Science and Technology of China, Hefei 230026, Anhui, China) Shifeng Mao (School of Nuclear Sciences and Technology, University of Science and Technology of China, Hefei 230026, Anhui, China) Yuntao Song (Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, Anhui, China;School of Nuclear Sciences and Technology, University of Science and Technology of China, Hefei 230026, Anhui, China) Zhongwei Wang (Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, Anhui, China)

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