VITAS: A multi-purpose simulation code for the solution of neutron transport problems based on variational nodal methods

Zhang, Tengfei; Wei, Xiao; Yin, Han; Sun, Qizheng; Liu, Xiaojing

doi:10.1016/j.anucene.2022.109335

Cited by 28 publications

(2 citation statements)

References 39 publications

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“…Analyses of fast reactors can be accomplished by either deterministic methods or stochastic methods. Deterministic codes that are established on the neutron transport theory can provide both accurate and efficient solutions to fast reactor problems (Zhang et al, 2022). In addition, the Monte Carlo method is flexible in geometrical modeling and is suited for highfidelity and accurate computations.…”

Section: Calculation Programmentioning

confidence: 99%

Research and analysis of the effect between the power level and economy on the lead-based modular nuclear power reactor

Lou

Wang²,

Zhou³

et al. 2022

Front. Energy Res.

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The fast reactor is gradually being paid attention to in nuclear power due to a better breeding effect, and its economy is also directly followed. Due to the restriction of the core power density, the core power level is directly related to the volume of the core active area. When the power level and the volume of the core gradually increase, the mass of uranium and 235U in the core at the beginning of life will gradually increase on the basis of a critical uranium inventory. At the same time, due to the gradual increase in the breeding effect, the utilization rate of uranium resources at the end of life will gradually increase. Due to the characteristics of the large critical uranium mass and high breeding effect, the mass of uranium and 235U in the low power level core at the beginning of life cannot be further reduced because of the critical uranium inventory. The lifetime of the high power level core should be extended to use the wealthy reactivity of the core because of the improvement in the breeding effect. However, due to the requirements of the nuclear power refuel time and the limitation to fuel consumption, the breeding effect brought by the improvement in the core power level and the size of the active zone may be less effective. In this article, the power level and economy of lead-based modular nuclear power are analyzed, and the economy of different power level fast reactors with 2,000 EFPD lifetime such as 100 MWt, 300 MWt, 500 MWt, 700 MWt, and 1000 MWt thermal power is designed and analyzed. By analyzing the invention of uranium and 235U and the fuel utilization of different core schemes, the best economic analysis of the single reactor power of the current lead-based modular reactor is proposed and the foundation of the lead-based modular nuclear power is provided.

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Section: Calculation Programmentioning

confidence: 99%

Research and analysis of the effect between the power level and economy on the lead-based modular nuclear power reactor

Lou

Wang²,

Zhou³

et al. 2022

Front. Energy Res.

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show abstract

“…Until now, the 2D/1D approximation technique has been applied to plentiful advanced neutronics simulation tools, such as DeCART (Joo et al, 2003), MPACT (Larsen et al, 2019), PROTEUS-MOC (Jung et al, 2018), nTRACER (Choi et al, 2018), NECP-X (Chen et al, 2018), OpenMOC (Boyd et al, 2014), and PANDAS-MOC (Tao and Xu, 2022c). Moreover, other deterministic methods, such as the variational nodal method (VNM), also exhibit the capability in handling arbitrarily complicated geometries and is developed and used in some prestigious neutronics codes, such as VITAS (Zhang et al, 2022).…”

Section: Introductionmentioning

confidence: 99%

Parallel schedules for MOC sweep in the neutron transport code PANDAS-MOC

Tao

Xu²

2022

Front. Nucl. Eng.

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Method of characteristics (MOC) is a commonly applied technique for solving the Boltzmann form of the neutron transport equation. In the PANDAS-MOC neutron transport code, MOC is used to determine the 2D radial solution. However, in the whole-code OpenMP threading hybrid model (WCP) of PANDAS-MOC, it is found that when using the classic parallelism, the MOC sweeping performance is restricted by the overhead incurred by the unbalanced workload and omp atomic clause. This article describes three parallel algorithms for the MOC sweep in the WCP model: the long-track schedule, equal-segment schedule, and no-atomic schedule. All algorithms are accomplished by updating the partition approach and rearranging the sweeping order of the characteristic rays, and their parallel performances are examined by the C5G7 3D core. The results illustrate that the no-atomic schedule can reach 0.686 parallel efficiency when using 36 threads, which is larger than the parallel efficiency obtained in the MPI-only parallelization model.

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On the transient models of the VITAS code: applications to the C5G7-TD pin-resolved benchmark problem

et al. 2023

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VITAS: A multi-purpose simulation code for the solution of neutron transport problems based on variational nodal methods

Cited by 28 publications

References 39 publications

Research and analysis of the effect between the power level and economy on the lead-based modular nuclear power reactor

Research and analysis of the effect between the power level and economy on the lead-based modular nuclear power reactor

Parallel schedules for MOC sweep in the neutron transport code PANDAS-MOC

On the transient models of the VITAS code: applications to the C5G7-TD pin-resolved benchmark problem

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