مقاله انگلیسی توسعه و کاربرد مقدماتی کد قطعی NECP-FISH برای آنالیز نوترونیکی پتوی راکتور همجوشی
Abstract
Keywords
Introduction
Theory and method
Framework and code development
Numerical results and analysis
Conclusions
Declaration of Competing Interest
Acknowledgments
References
Abstract
The fusion-reactor blanket is very important, as it is responsible for the tritium self-sustaining, energy gain, and radiation shielding. Due to the complex structure, large geometry size and inhomogeneous neutron-flux distribution, the Monte-Carlo method is widely used for the neutronics analysis of fusion-reactor blanket, but it takes a large amount of computational time for acceptable simulation results. The deterministic code is the better choice for the fusion-reactor blanket. The geometry capability and accuracy limitation are the most important issues for the deterministic code to simulate the fusionreactor blanket. Therefore, the newly deterministic code named NECP-FISH has been developed for the fusion-reactor blanket, in which the spherical harmonic function and finite element method were applied. Moreover, the open-source platform SALOME has been applied to generate the complex geometry as pre-process of NECP-FISH. As code verification, NECP-FISH has been applied to simulate the Breeding Unit of HCCB-DEMO, using Monte-Carlo code to provide the reference results. It can be observed that the simulation results of the tritium breeding ratio (TBR), neutron flux and heat release rate provided by NECP-FISH are agreed well with corresponding values by the Monte-Carlo code.
Introduction
The fusion-reactor blanket is very important, as it is responsible for the tritium self-sustaining, energy gain, and radiation shielding. However, the geometry of the fusion-reactor blanket is very complicated, as there are many irregular structures applied in the blanket. Therefore, the Monte-Carlo method has been widely applied to perform the neutronics analysis of the fusion-reactor blanket, because of its advantage in powerful capability for complex geometry. As improvement in geometry modeling, the Monte-Carlo codes McCad (Große et al., 2013) and MCAM (Wu, 2009) have been updated to automatically generate the input card based on the CAD files of fusion-reactor blanket. However, large amount of particles are required for the Monte-Carlo code to simulate the fusionreactor blanket, which takes a long computational time. Therefore, the deterministic method is another choice for the modeling and simulation of the fusion-reactor blanket.