Numerical simulation of stress properties on high-yield fast-neutron-burst reactor in super-prompt-critical condition

Chen Shuo; Zheng Chun; Du Jinfeng

doi:10.11884/HPLPB201931.180347

Volume 31 Issue 5

May 2019

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Citation:

Chen Shuo, Zheng Chun, Du Jinfeng. Numerical simulation of stress properties on high-yield fast-neutron-burst reactor in super-prompt-critical condition[J]. High Power Laser and Particle Beams, 2019, 31: 056004. doi: 10.11884/HPLPB201931.180347

Li Xin. Laser ray-tracing phenomenal model at far field[J]. High Power Laser and Particle Beams, 2015, 27: 032003. doi: 10.11884/HPLPB201527.032003

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Numerical simulation of stress properties on high-yield fast-neutron-burst reactor in super-prompt-critical condition

doi: 10.11884/HPLPB201931.180347

Chen Shuo^{1, 2
,},
Zheng Chun^{1, 2
,
,},
Du Jinfeng^{1, 2}

1.
Institute of Nuclear Physics and Chemistry, CAEP, Mianyang 621900, China
2.
Key Laboratory of Neutron Physics, CAEP, Mianyang 621900, China

Received Date: 2018-12-01
Rev Recd Date: 2019-01-25
Publish Date: 2019-05-15

Abstract

Abstract

The performance of fast burst reactor (FBR) is mainly restricted by the physical damage caused by the mechanical shock. The smaller burst width and larger fission yield in high-yield FBRs indicate more significant stress variation. To obtain the temporal and spatial distributions of stress/strain of burst in the high-yield FBR and to provide technical support for the design and safety analysis of new-type FBRs, the neutronic calculation based on the point kinetic approximation and Monte Carlo method is first performed to obtain the temporal and spatial distributions of fission power in the cylindrical FBR Godiva IV, the three-dimensional thermoelastic behavior in the burst is then simulated by using the finite element method software ANSYS Mechanical. The dynamic response of stress in material component is obtained and analyzed. The results show that the cylindrical fuel will suffer a stress wave during the burst and the maximum stress occurs in the radial cracking of central fuel rings.
- thermal shock stress,
- fast burst reactor,
- U-Mo,
- super-prompt-critical,
- cylindrical fuel component

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References(11)

References

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