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The development of CFETR integration design platform is in progress to accelerate the CFETR design in consideration of both core physics and engineering practicability. Within the engineering framework of CFETR integration design platform, the neutronics interface module has been implemented. This work presents the parameter study on helium cooled ceramic breeder blanket neutronics with the neutronics interface module of the CFETR integration design platform. The parameterized 3-D neutronic model of CFETR was set in the first place. Afterwards, the workflow of neutronic analyses was established. The concerned geometry and composition parameters of breeder blanket were selected as input and the tritium breeding ratio was selected as target. And, then, the workflow was abstracted as the mathematical model in the form of the so called response surface based on sufficient MCNP simulations. With the workflow or response surface model, the estimation and optimization of target parameter could be achieved. Finally, a set of local optimal parameters was proposed for CFETR helium cooled ceramic breeder blanket. [ABSTRACT FROM AUTHOR]

Highlights • An integrated analysis of blanket and EDPP is carried out with the conventional FE method code (ANSYS). • The EDPP has larger influence on the EM loads distribution of the IB blanket compared to the OB blanket. • A diagnostic port plug with small front openings could be useful to reduce its effect on the EM loads of the blanket system. Abstract The Chinese Fusion Engineering Test Reactor (CFETR) is the next step in China's research into fusion energy. In phase I, the preliminarily design of diagnostic systems for the CFETR was completed; however, the material and spatial position of the diagnostic systems severely affect EM loads distribution in blanket modules. In order to evaluate the effect of a diagnostic port plug on the EM loads distribution in the blanket system of CFETR, a finite element (FE) model with an equatorial diagnostic port plug (EDPP) was established using ANSYS. The EM forces and moments are calculated and discussed, followed by a comparison of EM loads in the helium-cooled ceramic breeder (HCCB) blanket to verify the EM effect of the EDPP. Simulation results show that the EM loads in the inboard (IB) and outboard (OB) blanket modules and segments were changed with the EDPP, but the direction of the main loads on the blanket system did not change. The results also show that the EDPP has a greater influence on the EM loads of the IB blanket compared to the OB blanket, meaning it is necessary to take into account the effect of the EDPP during the evaluation of the mechanical design of the blanket system in further studies. The investigation presented here may also serve as a technical reference for the design and optimization of diagnostic port plugs in the future. [ABSTRACT FROM AUTHOR]

Chinese Fusion Engineering Testing Reactor (CFETR) is aimed to obtain the technologies to fill the gaps between ITER and DEMO. The helium cooled ceramic breeder (HCCB) blanket is one of the candidates for CFETR. Ceramics Li 4 SiO 4 , beryllium and helium of 8 MPa were selected as tritium breeding material, neutron multiplier and coolant, respectively. CLF steel, one of reduced activation ferritic/martensitic (RAFM) steels, was applied as structural materials of blanket. Neutron and gamma transport was simulated with MCNP code and FENDL/MC-2.1 neutron cross section data. Activation calculation was performed with FISPACT-2007 code and EAF-2007 activation file. In this study, neutronics characteristic of HCCB blanket such as tritium breeding ratio (TBR) and shielding were assessed. The arrangement of Be, Li 4 SiO 4 and cooling plate in blanket module was optimized to improve TBR. The sensitive study for First Wall on TBR was also performed. The radioactivity inventories of HCCB blanket were estimated. The dominant radionuclides in structural materials, Li 4 SiO 4 and Beryllium were discussed, respectively. The damage of plasma facing components such as First Wall and divertor due to DT neutron irradiation was analyzed in terms of DPA value and gaseous product. [ABSTRACT FROM AUTHOR]