Safety analysis of LBLOCA in BDBA scenarios for the Bushehr's VVER-1000 nuclear power plant

Dose assessment of radionuclides dispersion from Bushehr nuclear power plant stack under normal operation and accident conditions

“…The effective Table 3 e Meteorological conditions used to define the atmospheric stability classes [10].…”

“…Depending on the physicochemical state of a radionuclide, its behavior in the confining system may be different, therefore in the FSAR of BNPP-1 four states of FPs in terms of their behavior including aerosols, inert radioactive gases (IRG 10 ), molecular iodine and organic iodine are considered [6]. Based on the thermal-hydraulic analysis of LBLOCA in Bushehr nuclear reactor by the end of the first day the pressure is reduced actually to the atmospheric pressure [10]. Therefore, in calculating the release of FPs it is conservatively assumed that the daily leakage from the steel containment in the first day is 0.25% whereas in the rest period is 0.11 percent of the containment volume [6].…”

Estimation of relative power distribution and power peaking factor in a VVER-1000 reactor core using artificial neural networks

“…The temperature profiles of coolant and fuel material are obtained by a verified model of VVER-1000 reactor based on Unit 1 of BNPP developed in RELAP5/ MOD3.2 code. The RELAP5 model consists of 4-loop primary and secondary systems with all their relevant sub-systems (Pirouzmand et al, 2014). The effect of S (alpha, beta) thermal scattering and the temperature influence on its value is also considered.…”

Development and Validation of a New Domestic Software for Dose Assessment during Normal and Accident Conditions in Nuclear Power Plants (NPPS)

“…Moreover, Sohrabi et al (2013a) assessed the individual and collective doses of the critical groups of the population who receive the highest dose from radioactive discharges into the environment (atmosphere and aquatic) under normal operating conditions using the PC-CREAM 98 computer code. The use of fully different software and different input parameters in Zali et al (2017), Pirouzmand et al (2015), and Pirouzmand et al (2016) for normal operation led to the different values of dose assessments. Furthermore, Sohrabi et al (2013a) estimated the radiation doses received by the public living around the site of the BNPP-1 due to an accidental release of radionuclides into the environment involving a hypothetical accident caused by the primary coolant leakage to the secondary circuit.…”