Long term station blackout analyses of two loop PWR using RELAP5/MOD3.3

被引:0
|
作者
Prosek, Andrej [1 ]
Cizelj, Leon [1 ]
机构
[1] Jozef Stefan Inst, Jamova Cesta 39, SI-1000 Ljubljana, Slovenia
关键词
D O I
暂无
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Stress tests which had to be performed in European countries required evaluation of the consequences of loss of safety functions from any initiating event (e.g., earthquake or flooding) causing loss of electrical power, including station blackout (SBO), loss of the ultimate heat sink or both. Long term SBO in a pressurized water reactor (PWR) leads to severe accident sequences, assuming that existing plant means (systems, equipment and procedures) are used for accident mitigation. Therefore the main objective was to study the accident management strategies for SBO scenarios (with different reactor coolant pumps (RCPs) leaks assumed) to delay the time before core uncovers and significantly heats up. The most important strategies assumed were primary side depressurization and additional makeup water to reactor coolant system (RCS). For simulations of long term SBO scenarios, including early stages of severe accident sequences, the latest best estimate RELAP5/MOD3.3 and the verified input model of Krsko two-loop PWR were used. The results suggest that for the expected magnitude of RCPs seal leak, the core uncovery during the first seven days could be prevented by using the turbine driven auxiliary feedwater pump and manually depressurizing the RCS through the secondary side. For larger RCPs seal leaks, in general this is not the case. Nevertheless, the core uncovery can be significantly delayed by increasing the RCS depressurization.
引用
收藏
页数:8
相关论文
共 50 条
  • [1] Long-Term Station Blackout Accident Analyses of a PWR with RELAP5/MOD3.3
    Prosek, Andrej
    Cizelj, Leon
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2013, 2013
  • [2] RELAP5/MOD3.3 Analyses for Prevention Strategy of Extended Station Blackout
    Prosek, Andrej
    Volkanovski, Andrija
    JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2015, 1 (04):
  • [3] RELAP5/MOD3.3 Best Estimate Analyses for Human Reliability Analysis
    Prosek, Andrej
    Mavko, Borut
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2010, 2010
  • [4] Assessment of RELAP5/MOD3.3 Against Single Rod Reflooding Experiments
    Lymperea, N.
    Nikoglou, A.
    Hinis, E.
    ASCE-ASME JOURNAL OF RISK AND UNCERTAINTY IN ENGINEERING SYSTEMS PART B-MECHANICAL ENGINEERING, 2018, 4 (03):
  • [5] Modeling of droplet diameter changes during reflood into RELAP5/Mod3.3
    Park, Ju Hyun
    Jeong, Yong Hoon
    NUCLEAR ENGINEERING AND DESIGN, 2022, 393
  • [6] Implementation of Lead-Lithium as working fluid in RELAP5/Mod3.3
    Barone, Gianluca
    Martelli, Daniele
    Forgione, Nicola
    FUSION ENGINEERING AND DESIGN, 2019, 146 : 1308 - 1312
  • [7] Improvement and validation of the wall heat transfer package of RELAP5/MOD3.3
    Wu, Pan
    Xiong, Xiaofei
    Shan, Jianqiang
    Gou, Junli
    Zhang, Bin
    Zhang, Bo
    NUCLEAR ENGINEERING AND DESIGN, 2016, 310 : 418 - 428
  • [8] RELAP5/MOD3.3 study on density wave instabilities in single channel and two parallel channels
    Colombo, Marco
    Cammi, Antonio
    Papini, Davide
    Ricotti, Marco E.
    PROGRESS IN NUCLEAR ENERGY, 2012, 56 : 15 - 23
  • [9] Integral loop test and assessment of modified RELAP5/MOD3.3 for RCS coolant inventory during a LBLOCA
    Kim, Yong-Soo
    Bae, Byoung-Uhn
    Park, Goon-Cherl
    NUCLEAR ENGINEERING AND DESIGN, 2007, 237 (02) : 182 - 198
  • [10] An assessment of RELAP5/Mod3.3 condensation model for high Reynolds number flows
    Aglar, Fahri
    PROGRESS IN NUCLEAR ENERGY, 2010, 52 (08) : 759 - 766