高产额脉冲堆爆发脉冲过程力学特性数值模拟

陈硕; 郑春; 杜金峰

doi:10.11884/HPLPB201931.180347

高产额脉冲堆爆发脉冲过程力学特性数值模拟

doi: 10.11884/HPLPB201931.180347

陈硕^{1, 2,},
郑春^{1, 2, ,},
杜金峰^{1, 2}

1.
中国工程物理研究院核物理与化学研究所, 四川绵阳 621900
2.
中国工程物理研究院中子物理学重点实验室, 四川绵阳 621900

基金项目:

国家自然科学基金项目 11775197

详细信息

作者简介:
陈硕(1993—), 男，硕士研究生，从事快中子脉冲堆安全研究; chenshuo_lice@163.com

通讯作者:
郑春(1971—), 男，研究员，从事辐射测量和临界安全研究; zhengchun@caep.cn

中图分类号: TL411
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- 被引次数: 0
出版历程
- 收稿日期: 2018-12-01
- 修回日期: 2019-01-25
- 刊出日期: 2019-05-15

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

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

摘要

摘要: 脉冲堆的性能主要受机械冲击引起的物理损伤的限制。高产额脉冲堆比CFBR-Ⅱ等金属铀脉冲堆追求更窄的脉冲宽度和更高的裂变产额，脉冲过程应力变化更加剧烈。为了获得高产额脉冲堆爆发脉冲过程中应力应变的分布，为新型脉冲堆设计和安全分析提供技术支持，基于圆柱型的铀钼合金快中子脉冲堆Godiva Ⅳ，以点堆方程以及MC(蒙特卡罗)方法对其中子产额以及功率分布进行了计算。并建立了快中子脉冲堆Godiva Ⅳ的三维模型，基于已知功率分布条件，利用有限元计算软件ANSYS Mechanical对其脉冲动态过程进行了瞬态的有限元计算，得到了Godiva Ⅳ圆柱型金属燃料在超临界脉冲爆发条件下的应力响应特性。
- 热冲击应力 /
- 脉冲堆 /
- 铀钼合金 /
- 超临界脉冲 /
- 圆柱型燃料
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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图 1 几何模型

Figure 1. Geometric model

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图 2 轴向中子通量分布

Figure 2. Axial distribution of neutron flux

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图 3 径向中子通量分布

Figure 3. Radial distribution of neutron flux

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图 4 反应堆功率、温升变化曲线

Figure 4. Temporal variations of power density and temperature rise

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图 5 中心燃料环正应力变化

Figure 5. Stress variation of fuel ring

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图 6 燃料环应变变化

Figure 6. Deformation of the fuel ring

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图 7 中心燃料环应力分布云图

Figure 7. Stress distribution of the central fuel ring

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图 8 安全块应力分布

Figure 8. Stress distribution of safety block

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表 1 U-1.5%Mo合金物性参数

Table 1. Parameters of the U-1.5%Mo

yield strength σ_0.2/GPa	ultimate tensile strength σ_u/GPa	Poission’s ratio ν	coefficient of thermal expansion/℃^-1	heat capacity C_p/ (J·kg^-1·℃^-1)
0.65	0.95	0.37	1.48×10^-5	140.3

bulk modulus K/GPa	shear modulus G/GPa	Young’s modulus E/GPa	heat capacity C_p/ (J·kg^-1·℃^-1)	density ρ/ (g·cm^-3)
100.77	28.7	78.60	29.4	18.47

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表 2 ANSYS计算结果与理论解对照表

Table 2. Theoretical solutions and ANSYS solutions

	outer surface				inner surface
	σ_{r, p}/MPa	σ_{r, b}/MPa	u_p/cm	u_b/cm	σ_{r, p}/MPa	σ_{r, b}/MPa	u_p/cm	u_b/cm
theoretical solutions	268.91	-264.08	0.060 2	0.029 2	557.81	-548.15	0.051 6	0.008 3
ANSYS (4-node tetrahedral element)	270.85	-265.01	0.060 3	0.029 2	556.84	-548.71	0.051 6	0.008 3
ANSYS (10-node tetrahedral element)	269.04	-263.88	0.060 3	0.029 3	555.49	-547.13	0.051 6	0.008 3

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参考文献(11)

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