Assessment of transient characteristics of fast reactors and influences of minor actinides using neutron transport method

2017 ◽  
Vol 41 (14) ◽  
pp. 2194-2205 ◽  
Author(s):  
Mingtao He ◽  
Youqi Zheng ◽  
Hongchun Wu ◽  
Zhuo Li ◽  
Xianan Du
Keyword(s):  
Neutron Transport ◽  
Minor Actinides ◽  
Fast Reactors ◽  
Transient Characteristics ◽  
Transport Method

scholarly journals The Application of the Combined Fission Matrix Theory in Fast Reactors

2021 ◽  
Vol 9 ◽  
Author(s):  
Donghao He ◽  
Tengfei Zhang ◽  
Xiaojing Liu
Keyword(s):  
High Efficiency ◽  
Matrix Theory ◽  
Neutron Transport ◽  
Thermal Reactor ◽  
Fast Reactors ◽  
Sodium Fast Reactor ◽  
The Monte Carlo Method ◽  
Transport Calculation ◽  
Rms Error ◽  
Transport Method

The combined fission matrix theory is a recently-developed hybrid neutron transport method. It features high efficiency, fidelity, and resolution whole-core transport calculation. The theory is based on the assumption that the fission matrix element ai,j is dominated by the property of the destination cell i. This assumption can be well explained in thermal reactors, and the combined fission matrix method has been validated in a series of thermal neutron system benchmarks. This work examines the feasibility of the combined fission matrix theory in fast reactors. The European Sodium Fast Reactor is used as the numerical benchmark. Compared to the Monte Carlo method, the combined fission matrix theory reports a 64 pcm keff difference and 8.3% 2D RMS error. The error is much larger than that in thermal reactors, and the correction ratio cannot significantly reduce the material discontinuity error in fast reactors. Overall, the combined fission matrix theory is more suited for thermal reactor transport calculations. Its application in fast reactors needs further developments.

scholarly journals The results of the transmuting minor actinides with thermal and fast reactors neutrons

2016 ◽  
Vol 2016 (2) ◽  
pp. 77-86 ◽  
Author(s):  
Yurij Alekseevich Kazansky ◽  
Nikolay Vital’evich Ivanov ◽  
Mihail Igorevich Romanov
Keyword(s):  
Minor Actinides ◽  
Fast Reactors

Beam transient analyses of Accelerator Driven Subcritical Reactors based on neutron transport method

2015 ◽  
Vol 295 ◽  
pp. 489-499 ◽  
Author(s):  
Mingtao He ◽  
Hongchun Wu ◽  
Youqi Zheng ◽  
Kunpeng Wang ◽  
Xunzhao Li ◽  
...  
Keyword(s):  
Neutron Transport ◽  
Transport Method

Interpretation of transmutation rates of minor actinides in thermal and fast reactors

1998 ◽  
Vol 25 (9) ◽  
pp. 653-665 ◽  
Author(s):  
Toshikazu Takeda ◽  
Hiroki Nakabayashi ◽  
Naoki Hirokawa
Keyword(s):  
Minor Actinides ◽  
Fast Reactors

scholarly journals A MULTIPHYSICS SIMULATION SUITE FOR SODIUM COOLED FAST REACTORS

2021 ◽  
Vol 247 ◽  
pp. 06019
Author(s):  
William C. Dawn ◽  
Scott Palmtag
Keyword(s):  
Power Distribution ◽  
Neutron Transport ◽  
Three Dimensional ◽  
Reactor Power ◽  
Fast Reactors ◽  
Feedback Effects ◽  
Radial Heat ◽  
Axial Heat ◽  
Neutron Transport Equations ◽  
Expansion Model

A simulation suite has been developed to model reactor power distribution and multiphysics feedback effects in Sodium-cooled Fast Reactors (SFRs). This suite is based on the Finite Element Method (FEM) and employs a general, unstructured mesh to solve the Simplified P3 (SP3) neutron transport equations. In the FEM implementation, two-dimensional triangular elements and three-dimensional wedge elements are selected. Wedge elements are selected for their natural description of hexagonal geometry common to fast reactors. Thermal feedback effects within fast reactors are modeled within the simulation suite. A thermal hydraulic model is developed, modeling both axial heat convection and radial heat conduction within fuel assemblies. A thermal expansion model is included and is demonstrated to significantly affect reactivity. This simulation suite has been employed to model the Advanced Burner Reactor (ABR) benchmark, specifically the MET-1000. It has been demonstrated that these models sufficiently describe the multiphysics feedback phenomena and can be used to estimate multiphysics reactivity feedback coefficients.

Fabrication of Fuel and Recycling of Minor Actinides in Fast Reactors

2010 ◽  
Vol 73 ◽  
pp. 97-103
Author(s):  
Joseph Somers
Keyword(s):  
Minor Actinides ◽  
Heterogeneous Reactor ◽  
Fast Reactors ◽  
Processing Methods ◽  
Inert Matrix Fuel ◽  
Inert Matrix ◽  
Neutron Transmutation

Fuels for future fast reactors will not only produce energy, but they must also actively contribute to the minimisation of long lived wastes produced by these, and other reactor systems. The fuels must incorporate minor actinides (MA = Np, Am, Cm) for neutron transmutation into short lived isotopes. Within Europe oxide fuels are favoured. Transmutation can be considered in homogeneous or heterogeneous reactor recycle modes (i.e. in fuels or targets, respectively). Fabrication of such fuels can be made by advanced liquid processing methods, enabling property determination and screening irradiation experiments. This paper will describe these fabrication processes, and discuss properties and fuel irradiation experiments made to date. Both fertile and inert matrix fuel types are considered.

Sign in / Sign up

Export Citation Format

Share Document