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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]

The China Fusion Engineering Test Reactor (CFETR) has been designed as steady-state operated tokamak device. The CFETR new engineering design has been initialized corresponding to the latest core parameters (major/minor radius is R = 7.2 m/a = 2.2 m). The nuclear analysis of CFETR was carried out to evaluate the neutron shielding capabilities and nuclear responses to toroidal field coils (TFC). The 3D neutronics model of CFETR was built with the support of McCad tool to convert the CAD model automatically. An extended variance reduction (VR) technique of combined MAGIC GVR with density reduction method has been involved to generate suitable weight windows to enhance the efficiency of particle transport. Highly detailed neutron and photon map has been obtained which meet the requirements for Monte Carlo nuclear analyses. The global neutron flux distribution of 3D CFETR with P f = 200 MW to 1.5 GW was obtained to evaluate its shielding performance. The nuclear responses to TFC such as the nuclear heating and fast neutron fluence have been evaluated. Initial results show the shielding of current divertor design is not sufficient and the optimizing work has been done. The final results satisfy the referred ITER design limit and it can provide the support for the future more detailed design of divertor and other shielding systems. [ABSTRACT FROM AUTHOR]

• 3D full neutronic model of CFETR ECRH was built to deliver the nuclear analysis • Operation dose of CFETR in the building above ECRH port is about 100 μSv/h • Shutdown dose rate at position C of ECRH is about 160 μSv/h 1 month after shutdown Electron Cyclotron Resonance Heating (ECRH) is one of auxiliary heating systems to be installed in CFETR. For heating purpose of ECRH, a penetration space has been designed to transmit the wave to plasma. This will significantly increase the neutrons streaming through the wave channel and result in heavy irradiation of ECRH port structures. For nuclear safety analysis, the irradiation dose during operation of CFETR should be limited according to the regulation of radiological zone. In case of failure, the ECRH is planned to be maintained by workers after shutdown and waiting time of one month until the dose rate decreases to low level of 100 μSv/h. The shielding capabilities of ECRH port has been evaluated in view of dose effect both during operation and after shutdown of CFETR. For that purpose, a 3-D neutronics model has been built to launch the nuclear analysis. The operation dose rate was directly transferred from the neutron and photon flux by using of ICRP-74 flux to dose conversion factors. The shutdown dose rate was obtained with NASCA code system by coupling the Monte Carlo particle transport and FISPACT activation calculation. The obtained operation and shutdown dose data can be provided for the shielding optimization of ECRH wave system. [ABSTRACT FROM AUTHOR]