scholarly journals Safety Assessment Framework for Nuclear Power Plant Decommissioning Workers

IEEE Access ◽  
2019 ◽  
Vol 7 ◽  
pp. 76305-76316
Author(s):  
Hyungjun Kim ◽  
Donghyun Lee ◽  
Choong Wie Lee ◽  
Hee Reyoung Kim ◽  
Seung Jun Lee
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Safety Assessment ◽  
Assessment Framework

Radiocarbon and Other Environmental Isotopes in the Groundwater of the Sites for a Planned New Nuclear Power Plant in Lithuania

Radiocarbon ◽  
2013 ◽  
Vol 55 (2) ◽  
pp. 951-962 ◽  
Author(s):  
Jonas Mažeika ◽  
Tõnu Martma ◽  
Rimantas Petrošius ◽  
Vaidotė Jakimavičiūtė-Maselienė ◽  
Žana Skuratovič
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Residence Time ◽  
Nuclear Power ◽  
Safety Assessment ◽  
Depth Interval ◽  
Near Surface ◽  
Helium Content ◽  
Aquifer System ◽  
Groundwater Residence Time

The assessment of construction sites for the new Visaginas Nuclear Power Plant (Visaginas NPP), including groundwater characterization, took place over the last few years. For a better understanding of the groundwater system, studies on radiocarbon; tritium; stable isotopes of hydrogen, oxygen, and carbon; and helium content were carried out at the location of the new NPP, at the Western and Eastern sites, as well as in the near-surface repository (NSR) site. Two critical depth zones in the Quaternary aquifer system were characterized by different groundwater residence times and having slightly different stable isotope features and helium content. The first shallow interval of the Quaternary multi-aquifer system consists of an unconfined aquifer and semiconfined aquifer. The second depth interval of the system is related to the lower Quaternary confined aquifer. Groundwater residence time in the first flow system was mainly based on tritium data and ranges from 6 to 60 yr. These aquifers are the most important in terms of safety assessment and are considered as a potential radionuclide transfer pathway in safety assessment. Groundwater residence time in the lower Quaternary aquifers based on 14C data varies from modern to several thousand years and in some intervals up to 10,500 yr.

Nonlinear Probabilistic Analysis of the Failure Pressure of NPP Shielding Plate

2016 ◽  
Vol 837 ◽  
pp. 214-221
Author(s):  
Juraj Kralik ◽  
Juraj Kralik Jr. ◽  
Maros Klabnik ◽  
Alzbeta Grmanova
Keyword(s):  
Monte Carlo ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Probabilistic Analysis ◽  
Nuclear Power ◽  
Safety Assessment ◽  
Fragility Curve ◽  
Failure Pressure ◽  
Surface Method ◽  
Central Composite

This paper describes the nonlinear probabilistic analysis of the failure pressure of the shielding plate of the reactor box of the nuclear power plant under a high internal overpressure and temperature. The scenario of the hard accident in Nuclear power plant (NPP) and the methodology of the calculation of the fragility curve of the failure overpressure using the probabilistic safety assessment PSA 2 level is presented. The fragility curve of the failure pressure was determined using 45 probabilistic simulations using the response surface method (RSM) with the Central Composite Design (CCD) for 106 Monte Carlo simulations for each model and 5 level of the overpressure.

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