Study of the thermal expansion effects of a space nuclear reactor with an integrated honeycomb core design using OpenMC and ANSYS

被引：1

作者：

Chen, Chao ^{[1
,2
]}

Mei, Huaping ^{[1
]}

Wang, Zhen ^{[1
]}

Zhang, Shichao ^{[1
]}

Liu, Shuyong ^{[1
]}

Wang, Haixia ^{[1
]}

Chen, Size ^{[1
]}

He, Meisheng ^{[1
]}

Li, Taosheng ^{[1
,2
]}

机构：

[1] Chinese Acad Sci, Inst Nucl Energy Safety Technol, Hefei Inst Phys Sci, Hefei 230031, Peoples R China

[2] Univ Sci & Technol China, Hefei 230027, Peoples R China

来源：

ANNALS OF NUCLEAR ENERGY | 2023年 / 191卷

关键词：

Heat pipe cooled reactor; Thermal expansion effect; Monte Carlo method; Finite element analysis; MATERIAL PROPERTY CORRELATIONS; URANIUM MONONITRIDE;

D O I：

10.1016/j.anucene.2023.109901

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

The negative reactivity feedback in the nuclear fuel plays an important role in maintaining the stable operation of nuclear reactors. For heat pipe cooled space reactors using highly enriched U, the fuel temperature reactivity feedback mainly due to Doppler effect and the thermal expansion of solid fuel. In this paper, based on an in-tegrated heat pipe space reactor design, a one-way coupling of the Monte Carlo code OpenMC and finite element method ANSYS is used to evaluate the reactor expansion and the impacts to the reactor reactivity. The average expansion was 0.126 cm for the fuel block from cold state to full power operation state. The fuel thermal expansion introduces a negative reactivity feedback of-59 pcm, and the reflector expansion introduces another-675 pcm, resulting a temperature coefficient of-0.638 pcm/K.

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页数：13

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