Rapid source term prediction in nuclear power plant accidents based on dynamic Bayesian networks and probabilistic risk assessment
Source term prediction plays an essential role in mitigating the consequences of nuclear
accidents and therefore is of practical importance. In this research, we propose a method for …
accidents and therefore is of practical importance. In this research, we propose a method for …
Modeling and simulation of radio-iodine released inside the containment as result of an accident
K Mehboob, MS Aljohani - Progress in Nuclear Energy, 2016 - Elsevier
Significant amount of radioactive iodine could release from a commercial Nuclear Power
Plant (NPP) in case of accident or due to rapture in primary loop piping. Quantification of …
Plant (NPP) in case of accident or due to rapture in primary loop piping. Quantification of …
Simulation and dose analysis of a hypothetical accident in Sanmen nuclear power plant
Y Zhu, J Guo, C Nie, Y Zhou - Annals of Nuclear Energy, 2014 - Elsevier
In November 2013, an AP1000 nuclear power plant (NPP) will be put into commercial
operation. An atmospheric dispersion of radionuclides during a severe hypothetical accident …
operation. An atmospheric dispersion of radionuclides during a severe hypothetical accident …
[HTML][HTML] A receptor-centric decision support system for the mitigation of nuclear power atmospheric release incidents
AM Ali, KE Kakosimos - Reliability Engineering & System Safety, 2023 - Elsevier
The history of incidents involving nuclear power plants underscores the imperative for robust
consequence assessment and countermeasure plans. Additionally, the recent energy crisis …
consequence assessment and countermeasure plans. Additionally, the recent energy crisis …
Investigation of small break LOCA with failure of the emergency core cooling system accident management in VVER-1000 reactor type
N Vahman, M Ghasemi, R Amrollahi, M Sohrabi - Annals of Nuclear Energy, 2023 - Elsevier
In this study, the thermohydraulic condition of the power plant is estimated as a result of the
Small Break Loss of Coolant Accident (SB-LOCA) for Bushehr Nuclear Power Plant (BNPP) …
Small Break Loss of Coolant Accident (SB-LOCA) for Bushehr Nuclear Power Plant (BNPP) …
Quantification of in-containment fission products source term for 1000 MWe PWR under loss of coolant accident
The aim of this work is the modeling and simulation of in-containment fission products (FPs)
quantification and behavior under loss of coolant accident (LOCA) in terms of NUREG-1465 …
quantification and behavior under loss of coolant accident (LOCA) in terms of NUREG-1465 …
Implications of local scale meteorological data on radioactive plume dispersion and dose delivery for a hypothetical severe accident at PARR-1
An assessment of radiological risk for the Pakistan Research Reactor (PARR-1) has been
conducted using International Radiological Assessment System (InterRAS) code. The …
conducted using International Radiological Assessment System (InterRAS) code. The …
Study of in-containment source term behavior for VVER-1000 under LOCA conditions using the IRBURN code system
S Jafarikia, SAH Feghhi - Annals of Nuclear Energy, 2018 - Elsevier
The purpose of this paper is to present a kinetic model for simulation and calculation of in-
containment activity in LWR power reactors after severe accidents. In-containment accident …
containment activity in LWR power reactors after severe accidents. In-containment accident …
Derivation of the source term, dose results and associated radiological consequences for the Greek Research Reactor–1
C Pappas, A Ikonomopoulos, A Sfetsos… - … Engineering and Design, 2014 - Elsevier
The estimated source term, dose results and radiological consequences of selected
accident sequences in the Greek Research Reactor–1 are presented and discussed. A …
accident sequences in the Greek Research Reactor–1 are presented and discussed. A …
Derivation of radiological source term of Korean design system-integrated modular advanced ReacTor (SMART)
K Mehboob, MS Aljohani - Annals of Nuclear Energy, 2018 - Elsevier
In this work, a study has been conducted to carry out a qualitative analysis for the evaluation
of radiation exposure from SMART reactor. Since SMART reactor is large LOCA proof …
of radiation exposure from SMART reactor. Since SMART reactor is large LOCA proof …