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The lead-bismuth cooled fast reactor (LFR) is one of the fourth-generation advanced reactors, which has the advantages of enhanced safety and high efficiency. However, the steam generator tube rupture (SGTR) accident is an important design-based accident in safety analysis, which may cause a severe threat to the integrity of the reactor system. In this paper, a numerical method was established to simulate the interaction of high-pressure water injection with lead-bismuth, and validated against the LIFUS5 experiment. A sensitivity analysis of the effect of water and lead-bismuth parameters on the water flow rate, vapor generation, and pressure evolution was conducted. The results indicated that the vapor generation at the early time was mainly caused by the water flash evaporation, followed by an accelerated vapor generation rate due to the enhanced heat transfer resulting from the vapor bubble fragmentation and the direct contact of lead-bismuth with water. It was found that a significant temperature gradient existed at the vapor and lead-bismuth interface. There was a pressure spike at the impact of water injection to the lead-bismuth, followed by a continuous increase of the overall pressure and the final stable pressure in the lead-bismuth vessel exceeded the initial water injection pressure. Sensitivity analysis results indicated that, as the water injection pressure increased, the water flow rate, vapor mass, and pressure in the vessel increased significantly, but the temperatures of water and lead-bismuth had little influence on the interactions

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참고문헌 (25건) : 자료제공( 네이버학술정보 )

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번호 참고문헌 국회도서관 소장유무
1 LIFUS5/Mod2: The Experimental Facility for HLM/Water Interaction Investigation 미소장
2 LBE–water interaction in sub-critical reactors: First experimental and modelling results 미소장
3 Experimental and computational investigation of LBE–water interaction in LIFUS 5 facility 미소장
4 LBE–water interaction in LIFUS 5 facility under different operating conditions 미소장
5 Preliminary investigation on the primary heat exchanger lower head rupture accident of forced circulation LBE-cooled fast reactor 미소장
6 Evaluation of a steam generator tube rupture accident in an accelerator driven system with lead cooling 미소장
7 The Surface Tension of Liquid Near-Eutectic Alloys of Lead–Bismuth System 미소장
8 Overview of steam generator tube degradation and integrity issues 미소장
9 A review of research progress in heat exchanger tube rupture accident of heavy liquid metal cooled reactors 미소장
10 Steam generator leakage in lead cooled fast reactors: Modeling of void transport to the core 미소장
11 Experimental and Numerical Analysis of Steam Generator Tube Rupture Event for MYRRHA Reactor in CIRCE Facility With SIMMER-IV Code 미소장
12 Review of Thermal-Hydraulic Issues and Studies of Lead-based fast reactors 미소장
13 RELAP5/SIMMER-III code coupling development for PbLi-water interaction 미소장
14 Numerical investigation on LBE-water interaction for heavy liquid metal cooled fast reactors 미소장
15 Experimental investigation on flow and heat transfer characteristics of lead–bismuth eutectic in circular tubes 미소장
16 Assessment of SIMMER-III code in predicting Water Cooled Lithium Lead Breeding Blanket “in-box-Loss of Coolant Accident” 미소장
17 Numerical simulation of bubble transport during steam generator tube rupture accident of Lead-cooled Fast Reactor 미소장
18 Experimental study on pressurization characteristics of a water droplet entrapped in molten LBE pool 미소장
19 Preliminary development and validation of ACENA code for heavy liquid metal-gas two phase flow simulation 미소장
20 Flow and heat transfer analysis of lead–bismuth eutectic flowing in a tube under rolling conditions 미소장
21 Numerical simulation of micro-crack leakage on steam generator heat transfer tube 미소장
22 Experimental investigation of pressure fluctuation and steam transport under SGTR accident in Lead-cooled Fast Reactors 미소장
23 Three-dimensional numerical simulation of the interaction between high-pressure sub-cooled water jet impacting high-temperature liquid lead-bismuth metal 미소장
24 Experimental investigation on the interaction characteristics of lead‑bismuth liquid metal and water 미소장
25 Addressing the heavy liquid metal – Water interaction issue in LBE system 미소장

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