激光惯性约束聚变堆包层能量沉积特性

李昕泽; 张冰倩; 陈荣华; 张魁; 张大林; 田文喜; 秋穗正; 苏光辉

doi:10.11884/HPLPB202436.240098

激光惯性约束聚变堆包层能量沉积特性

doi: 10.11884/HPLPB202436.240098

西安交通大学核科学与技术学院，西安 710049

详细信息

作者简介:
李昕泽，lxz159753@stu.xjtu.edu.cn

通讯作者:
陈荣华，rhchen@mail.xjtu.edu.cn。

中图分类号: TL645
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- 被引次数: 0
出版历程
- 收稿日期: 2024-03-18
- 修回日期: 2024-06-06
- 录用日期: 2024-06-06
- 网络出版日期: 2024-06-13
- 刊出日期: 2024-07-04

Energy deposition characteristics of tritium breeding blanket in laser inertial confinement fusion reactor

Department of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China

摘要

摘要: 参考国内外聚变堆技术，建立了一种200 MW激光惯性约束聚变堆包层概念设计，包层采用超临界二氧化碳和锂铅双冷结构。研究构建了瞬态和稳态耦合模型计算包层温度分布及变化。靶丸内爆反应使用MULTI-IFE进行计算，核热耦合部分基于蒙特卡罗程序OpenMC和自编程换热模型对包层模型结构、冷却和产氚进行计算。研究结果表明，核热耦合模型能够完成对包层的初步计算分析，周期性的瞬态载荷会引起第一壁面温度的振荡，但包层内部的温度最终会收敛到稳态计算结果。堆腔尺寸对于降低温度以及震荡效果明显，但仍需氙展平辐射功率峰。包层产氚和能量导出同时受到堆腔尺寸和增殖区的影响，在200 MW工况下，3 m半径和0.25 m增殖区尺寸计算结果最能满足需求。
- 激光聚变 /
- 聚变包层 /
- 核热耦合 /
- 能量沉积
Abstract: This study presents a conceptual design of a 200 MW laser Inertial Confinement Fusion (ICF) reactor blanket, referring to fusion reactor technologies. The blanket employs a dual-coolant structure consisting of supercritical CO₂ (S-CO₂) and liquid lead-lithium (PbLi). Transient and steady-state coupled models are established to calculate the temperature distribution and variations within the blanket. The implosion of the pellets is computed using MULTI-IFE. The nuclear heat coupling part is based on the Monte Carlo program OpenMC and self-programmed heat transfer models to calculate the blanket’s structure, cooling, and tritium production. The research findings indicate that the nuclear heat coupling model can complete preliminary calculations and analysis of the blanket. Periodic transient loads cause oscillations in the temperature of the first wall surface, but the temperature inside the blanket eventually converges to the steady-state calculation results. The reactor size significantly affects temperature reduction and oscillation effects, but it still requires xenon to flat radiation power peak. Both tritium production and energy export from the blanket are influenced by the reactor cavity size and the size of the breeding zone. Under the 200 MW operating conditions, it shows that a 3 m radius and a 0.25 m breeding zone size best meet the requirements.
- laser inertial confinement fusion /
- tritium breeding blanket /
- neutronics-thermal coupling /
- energy deposition

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图 1 包层模型

Figure 1. Blanket model

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图 2 流道布置

Figure 2. Arrangement of cooling channels

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图 3 内爆迹线图

Figure 3. Implosion trajectories

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图 4 X射线辐射输出

Figure 4. X-ray radiation

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图 5 归一化D-T反应率

Figure 5. Normalized D-T reaction rate

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图 6 反应率分区

Figure 6. Reaction rate zone

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图 7 计算模型

Figure 7. Model for calculation

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图 8 迭代流程

Figure 8. Iterative process

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图 9 瞬态加载方案

Figure 9. Transient loading scheme

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图 10 温度记录点

Figure 10. Temperature recording node

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图 11 温度计算结果

Figure 11. Temperature calculation results

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图 12 节点温度

Figure 12. Node temperature

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表 1 沉积热偏差

Table 1. Deposition heat deviation

No.	ratio of reaction numbers/%	error/%
1	1.4	0.75
2	24.4	−0.38
3	2.9	0.61

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表 2 PbLi物性参数

Table 2. PbLi properties

parameter	unit	temperature dependent correlation equations
ρ	kg·m⁻³	$\rho = 10\;520.0 - 1.189T$
c_p	J·kg⁻¹·K⁻¹	${c_p} = 194.74 - 9.0 \times {10^{ - 3}}T$
h	J·kg⁻¹	$h = 194.74\left( {T - {T_{\text{m}}}} \right) - 4.5 \times {10^{ - 3}}\left( {{T^2} - T_{\text{m}}^{\text{2}}} \right)$
λ	W·m⁻¹·K⁻¹	$\lambda = 1.9463 + 1.96 \times {10^{ - 2}}T$
μ	Pa·s	$ \; \mu =0.009\;14-1.774\;59\times {10}^{-5} T+9.552\;1\times {10}^{-9} {T}^{2} $

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表 3 震荡后节点温度

Table 3. Node temperatures after fluctuation (℃)

No.	transient state temperature			steady state temperature			transient state temperature with xenon
No.	3 m	4 m	5 m	3 m	4 m	5 m	3 m
1	683.23	571.49	516.61	682.97	566.57	513.72	683.61
2	674.44	566.84	513.62	670.23	559.69	509.31	671.41
3	601.31	527.63	488.72	598.03	520.35	484.33	600.70
4	448.40	439.50	437.88	448.83	440.62	436.79	448.87
5	456.10	445.15	443.25	456.59	446.78	442.20	456.24
6	437.26	437.36	436.73	437.28	435.90	435.23	437.18
7	432.66	432.89	432.36	432.68	431.53	430.96	432.60
8	432.50	432.80	432.30	432.51	431.43	430.90	432.53
9	437.07	437.25	436.66	437.08	435.78	435.15	437.10
10	434.68	435.79	435.70	434.41	434.23	434.13	434.07
11	430.50	431.57	431.50	430.28	430.13	430.05	430.66
12	430.48	431.56	431.49	430.26	430.11	430.04	430.65
13	434.66	435.78	435.69	434.39	434.21	434.12	434.06
14	434.30	435.55	435.55	433.99	433.97	433.96	434.91
15	430.18	431.37	431.36	429.93	429.91	429.91	430.52
16	421.47	422.24	422.24	420.03	420.02	420.01	421.21
17	421.78	422.68	422.68	420.03	420.02	420.01	421.94

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表 4 耦合模型对比结果

Table 4. Comparison results of coupled models

radius of vessel/m	size of breeding zone/m	tritium breeding ratio	PbLi energy export proportion/%	S-CO₂ mass flow rate/(kg/s)	PbLi mass flow rate/(kg/s)
3	0.15	1.289	64	5.835	14.40/6.27/2.15
	0.20	1.491	67	5.717	17.40/6.09/1.74
	0.25	1.596	69	5.635	19.70/5.50/1.30
4	0.15	1.297	59	6.819	13.30/5.66/1.84
	0.20	1.496	61	6.778	14.10/5.47/1.46
	0.25	1.599	62	6.732	18.20/4.90/1.05
5	0.15	1.301	49	8.469	11.30/4.64/1.36
	0.20	1.499	51	8.564	13.70/4.47/1.03
	0.25	1.600	52	8.584	15.60/3.97/0.67

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