Sensitivity analysis of large leakage sodium-water reaction protection system critical parameters with paralleling steam generators in a sodium-cooled fast reactor

Xi BAI; Peiwei SUN; Gang LUO; Huasong CAO; Xinyu WEI

doi:10.11889/j.0253-3219.2023.hjs.46.120603

NUCLEAR TECHNIQUES, Volume. 46, Issue 12, 120603(2023)

Sensitivity analysis of large leakage sodium-water reaction protection system critical parameters with paralleling steam generators in a sodium-cooled fast reactor

Xi BAI¹, Peiwei SUN^1、*, Gang LUO², Huasong CAO³, and Xinyu WEI¹

Author Affiliations

¹School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China

²Nuclear Power Institute of China, Chengdu 610012, China

³Xi'an Thermal Power Research Institute Co. Ltd, Xi'an 710054, China

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Figures & Tables(18)

Fig. 1. Structural diagram of the secondary loop in sodium-cooled fast reactor

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Fig. 2. Relationship diagram of large leakage SWR model

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Fig. 3. Diagram of hydrogen bubble transition from the spherical to columnar model

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Fig. 4. Diagram of SWR experiment system

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Fig. 5. Fitting curve of pressure input in reaction zone

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Fig. 6. Comparison of calculated and experimental pressure at secondary loop critical equipment

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Fig. 7. Pressure response of secondary loop critical equipment

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Fig. 8. Flow rate response of sodium in SGs

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Fig. 9. Pressure response of tank gas chamber

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Fig. 10. Sodium flow rate of damaged SG rupture disk

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Fig. 11. Sodium release flow rate of damaged SG module at different liquid rupture disk bursting pressures

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Fig. 12. Sodium release flow rate of damaged SG module at different rupture disk bursting delay times

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Fig. 13. Sodium release flow rate of damaged SG module at different liquid rupture disk locations

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Fig. 14. Sodium release flow rate damaged SG module at different release pipe lengths

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Fig. 15. Sodium release flow rate of damaged SG module at different primary accident discharge tank volumes

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Table 1. Critical parameters of protection system in secondary loop

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Table 1. Critical parameters of protection system in secondary loop

设备Equipment	参数Parameter
蒸汽发生器爆破片位置Location of rupture disk at SG	下腔室 Bottom chamber
SG爆破片爆破压力Bursting pressure of rupture disks at SG / MPa	1.0
缓冲罐气腔爆破片爆破压力Bursting pressure of rupture disk at the surge tank gas chamber / MPa	0.35
二级事故排放罐气腔爆破片爆破压力 Bursting pressure of rupture disk at secondary accident discharge tank gas chamber / MPa	0.5
爆破片爆破延迟时间Bursting delay time of rupture disks / s	0.02

Table 2. Critical parameters of protection system in secondary loop

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Table 2. Critical parameters of protection system in secondary loop

设备 Equipment	压力峰值 Peak pressure / MPa	压力峰值出现时间 Time of the peak pressure / s
泵Pump	0.894	0.139
中间热交换器Intermediate heat exchanger	1.329	0.188
钠流量分配器Sodium flow distributor	1.070	0.049
事故SG模块Damaged SG module	2.003	0.052
正常模块蒸汽发生器Normal SGs module	0.669	0.197
缓冲罐Surge tank	0.241	2.500
一级事故排放罐Primary accident discharge tank	0.052	2.500
二级事故排放罐Secondary accident discharge tank	0.051	2.500

Table 3. Maximum pressure of the critical equipment in secondary loop

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Table 3. Maximum pressure of the critical equipment in secondary loop

敏感性参数 Sensitivity parameter	模拟工况 Simulation conditions	SWR压力峰值 SWR pressure spike / MPa	IHX压力峰值 IHX pressure spike / MPa	PADT压力峰值 PADT pressure spike / MPa	SH爆破时间 SH bursting time / s	EV爆破时间 EV bursting time / s	出口报警时间 Outlet alarming time / s	入口报警时间 Input alarming time / s
液相爆破片爆破压力 Bursting pressure of liquid rupture disks	0.8 MPa	1.993	1.327	0.052	0.027	0.033	0.024	0.04
	1.0 MPa	2.003	1.329	0.052	0.028	0.036	0.024	0.04
	1.2 MPa	2.057	1.342	0.052	0.037	0.040	0.024	0.042
爆破片爆破延迟时间 Bursting delay time of rupture disks	0.02 s	2.003	1.329	0.052	0.028	0.036	0.024	0.04
	0.07 s	2.147	1.411	0.052	0.078	0.086	0.024	0.04
	0.12 s	2.147	1.441	0.052	0.128	0.136	0.024	0.04
液相爆破片位置 Location of the liquid rupture disks	上腔室 Upper chamber	1.997	1.339	0.052	0.033	0.036	0.024	0.04
液相爆破片位置 Location of the liquid rupture disks	下腔室 Bottom chamber	2.003	1.329	0.052	0.028	0.036	0.024	0.04
泄放管长度 Length of release pipe	减小到80% Decreased to 80 percentage	1.983	1.309	0.052	0.028	0.036	0.024	0.04
	不变Unchanged	2.003	1.329	0.052	0.028	0.036	0.024	0.04
	增大到1.2 Increased to 120 percentage	2.020	1.344	0.052	0.029	0.036	0.024	0.04
一级事故排放罐体积 Volume of PADT	减小到50% Decreased to 50 percentage	2.003	1.329	0.054	0.028	0.036	0.024	0.040
	不变Unchanged	2.003	1.329	0.052	0.028	0.036	0.024	0.04
	增大到1.5 Increased to 150 percentage	2.003	1.329	0.051	0.028	0.036	0.024	0.04

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Xi BAI, Peiwei SUN, Gang LUO, Huasong CAO, Xinyu WEI. Sensitivity analysis of large leakage sodium-water reaction protection system critical parameters with paralleling steam generators in a sodium-cooled fast reactor[J]. NUCLEAR TECHNIQUES, 2023, 46(12): 120603

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Paper Information

Category: Research Articles

Received: May. 26, 2023

Accepted: --

Published Online: Mar. 7, 2024

The Author Email: Peiwei SUN (孙培伟)

DOI:10.11889/j.0253-3219.2023.hjs.46.120603

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