System scaling analysis for modeling small break LOCA using the FULL SPECTRUM LOCA evaluation model

Liao, Jun

doi:10.1016/j.anucene.2015.09.014

Cited by 6 publications

(3 citation statements)

References 9 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Montero-Mayorga investigated SBLOCA with different break sizes with the best estimate TRACE V5.0 codes, and the main results show the similar trend when compared to Westinghouse NOTRUMP code [21]. Other scholars also conducted similar studies on SBLOCA of loop-type PWR, and some even investigated severe accidents phenomena caused by SBLOCA (the PCCS did not put into use on time) [22][23][24][25][26][27]. However, in this paper, a revised PSIS for GBS Qinshan I has been proposed.…”

Section: Introductionmentioning

confidence: 73%

RELAP5 Foresight Thermal-Hydraulic Analysis of Hypothesis Passive Safety Injection System under LOCA for an Existing NPP in China

Sun

Wang

et al. 2020

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

Qinshan nuclear power plant is the first large Chinese-designed nuclear power station based on pressurized water reactor, and the second generation main stream active safety injection system is adopted for Qinshan nuclear power plant. In this paper, a novel passive safety injection system (PSIS) has been proposed for ocean-based Qinshan Phase One nuclear power plant to replace the original active one. The PSIS contains high-pressure, medium-pressure, and lower-pressure safety injection systems, and a two-stage automatic depressurization system. To evaluate the system performance, small-break LOCA has been investigated using RELAP5. Various break sizes and locations including 2-inch, 10-inch cold leg break, and double-ended direct vessel injection line break were analyzed. Key safety parameters such as safe injection mass flow rates, coolant level of the core, system pressure, and fuel cladding temperature were monitored during the accident process. The results illustrate that the performance of the safety injection system can guarantee the effective core cooling and submerged under different LOCA even with only half of the safety injection system, which can fulfill the single failure criteria. The thermal-hydraulic analysis for the Qinshan passive safety injection system is significant to master the related technologies for Chinese engineer and develop the Chinese-designed third-generation nuclear power plants, and the PSIS can guarantee the reactor submerged under LOCA even plus the station block out accident.

show abstract

Section: Introductionmentioning

confidence: 73%

RELAP5 Foresight Thermal-Hydraulic Analysis of Hypothesis Passive Safety Injection System under LOCA for an Existing NPP in China

Sun

Wang

et al. 2020

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

show abstract

“…The LOBI facility is an integral thermal-hydraulic test facility built by the nuclear research institute of European atomic energy community, which is used for the experimental validation of prototypical large-scale pressurized water reactor [20,21].…”

Section: Simulation Of the Lobi Test Facilitymentioning

confidence: 99%

Coupling Design and Validation Analysis of an Integrated Framework of Uncertainty Quantification

Pang

Wang

et al. 2023

Energies

View full text Add to dashboard Cite

The uncertainty quantification is an indispensable part for the validation of the nuclear safety best-estimate codes. However, the uncertainty quantification usually requires the combination of statistical analysis software and nuclear reactor professional codes, and it consumes huge computing resources. In this paper, a design method of coupling interface between DAKOTA Version 6.16 statistical software and nuclear reactor professional simulation codes is proposed, and the integrated computing workflow including interface pre-processing, code batching operations, and interface post-processing can be realized. On this basis, an integrated framework of uncertainty quantification is developed, which is characterized by visualization, convenience, and efficient computing. Meanwhile, a typical example of small-break LOCA analysis of the LOBI test facility was used to validate the reliability of the developed integrated framework of uncertainty quantification. This research work can provide valuable guidance for developing an autonomous uncertainty analysis platform in China.

show abstract

“…34 Wulff and Rohatgi (1998) analyzed the scaling effects between an AP600 reactor and three test facilities (APEX, LSTF and SPES) during a 1inch Cold-Leg break. Furthermore, 36 Liao (2016) and 33 Muñoz-Cobo et al ( 2018) presented the application of this scaling analysis between a test facility, LSTF, and a Westinghouse 3-loop PWR for two different SBLOCA transients.…”

Section: Global System Scaling Analysismentioning

confidence: 99%

Scaling analysis of an IBLOCA counterpart test between the ATLAS and LSTF facilities

Lorduy-Alós

Gallardo

Verdú

2020

Progress in Nuclear Energy

View full text Add to dashboard Cite

System scaling analysis for modeling small break LOCA using the FULL SPECTRUM LOCA evaluation model

Cited by 6 publications

References 9 publications

RELAP5 Foresight Thermal-Hydraulic Analysis of Hypothesis Passive Safety Injection System under LOCA for an Existing NPP in China

RELAP5 Foresight Thermal-Hydraulic Analysis of Hypothesis Passive Safety Injection System under LOCA for an Existing NPP in China

Coupling Design and Validation Analysis of an Integrated Framework of Uncertainty Quantification

Scaling analysis of an IBLOCA counterpart test between the ATLAS and LSTF facilities

Contact Info

Product

Resources

About