Occupational internal exposure calculation during dismantling of bio-shield of Kori nuclear power plant unit#1

2020 ◽  
Vol 126 ◽  
pp. 103401
Author(s):  
ChoongWie Lee ◽  
Donghyun Lee ◽  
Hee Reyoung Kim ◽  
Seung Jun Lee
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Internal Exposure ◽  
Nuclear Power Plant Unit

Assessment of Internal Exposure Doses in Fukushima by a Whole Body Counter Within One Month after the Nuclear Power Plant Accident

2013 ◽  
Vol 179 (6) ◽  
pp. 663-668 ◽  
Author(s):  
Naoki Matsuda ◽  
Atsushi Kumagai ◽  
Akira Ohtsuru ◽  
Naoko Morita ◽  
Miwa Miura ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Internal Exposure ◽  
Whole Body ◽  
Nuclear Power Plant Accident ◽  
Body Counter ◽  
Whole Body Counter

Risk Based Inspection Pilot Study of Ignalina Nuclear Power Plant, Unit 2

2002 ◽  
Author(s):  
Bjorn Brickstad ◽  
Adam Letzter ◽  
Arturas Klimasauskas ◽  
Robertas Alzbutas ◽  
Linas Nedzinskas ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Pilot Study ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Fracture Mechanics ◽  
Nuclear Power ◽  
Damage Mechanism ◽  
Core Damage ◽  
Steel Welds ◽  
Nuclear Power Plant Unit

A project with the acronym IRBIS (Ignalina Risk Based Inspection pilot Study) has been performed with the objective to perform a quantitative risk analysis of a total of 1240 stainless steel welds in Ignalina Nuclear Power Plant, unit 2 (INPP-2). The damage mechanism is IGSCC and the failure probabilities are quantified by using probabilistic fracture mechanics. The conditional core damage probabilities are taken from the plant PSA.

scholarly journals Estimated internal exposure doses due to indoor radiocaesium contamination in residential houses after the Fukushima nuclear accident

2020 ◽  
Vol 10 (1) ◽  
Author(s):  
Hiroko Yoshida-Ohuchi ◽  
Naohide Shinohara
Keyword(s):  
Particle Size ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
House Dust ◽  
Nuclear Power ◽  
Measured Data ◽  
Internal Exposure ◽  
Effective Doses ◽  
Fukushima Daiichi ◽  
Work First

Abstract This work first reports the estimation of the internal exposure from ingestion of house dust and inhalation of aerosol, by employing a measured data on 137Cs activities, bioaccessibility (solubility to water and 1 M HCl), and particle size distribution. The house dust and aerosol samples were collected during the actual indoor cleaning by vacuuming and dusting, from 65 houses and buildings in proximity to the Fukushima Daiichi nuclear power plant (FDNPP) (1.6–16.1 km from the FDNPP) during a period from April 2016 to January 2019. Committed effective doses for an adult owing to the ingestion of house dust of 20 mg per day, which adheres to one’s hands through the hand-to-mouth, and those owing to inhalation of aerosol during dusting for 1.5 h while wearing a mask, were calculated using DCAL software for each house or building, as 1.13 µSv and 4.55 µSv as maximum doses, respectively (as of March 2011). Both the committed effective doses, owing to ingestion and inhalation, were inversely correlated with the distance from the FDNPP, and positively correlated with the indoor surface contamination.

Accident Analysis of Fukushima Daiichi Nuclear Power Plant Unit 2 by the SAMPSON Severe Accident Code

2014 ◽  
Author(s):  
Atsuo Takahashi ◽  
Marco Pellegrini ◽  
Hideo Mizouchi ◽  
Hiroaki Suzuki ◽  
Masanori Naitoh
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Cooling System ◽  
Severe Accident ◽  
Accident Analysis ◽  
Unknown Boundary ◽  
Long Time ◽  
Fukushima Daiichi ◽  
Nuclear Power Plant Unit

The transient process of the accident at the Fukushima Daiichi Nuclear Power Plant Unit 2 was analyzed by the severe accident analysis code, SAMPSON. One of the characteristic phenomena in Unit 2 is that the reactor core isolation cooling system (RCIC) worked for an unexpectedly long time (about 70 h) without batteries and consequently core damage was delayed when compared to Units 1 and 3. The mechanism of how the RCIC worked such a long time is thought to be due to balance between injected water from the RCIC pump and the supplied mixture of steam and water sent to the RCIC turbine. To confirm the RCIC working conditions and reproduce the measured plant properties, such as pressure and water level in the pressure vessel, we introduced a two-phase turbine driven pump model into SAMPSON. In the model, mass flow rate of water injected by the RCIC was calculated through turbine efficiency degradation the originated from the mixture of steam and water flowing to the RCIC turbine. To reproduce the drywell pressure, we assumed that the torus room was flooded by the tsunami and heat was removed from the suppression chamber to the sea water. Although uncertainties, mainly regarding behavior of debris, still remain because of unknown boundary conditions, such as alternative water injection by fire trucks, simulation results by SAMPSON agreed well with the measured values for several days after the scram.

Public Health Concerns on Radiation Exposure After the Fukushima Daiichi Nuclear Power Plant Accident

2015 ◽  
Vol 10 (sp) ◽  
pp. 716-727 ◽  
Author(s):  
Reiko Kanda ◽  
◽  
Satsuki Tsuji ◽  
Hidenori Yonehara ◽  
Masami Torikoshi ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Radiation Exposure ◽  
Media Coverage ◽  
Nuclear Power ◽  
Daily Life ◽  
Internal Exposure ◽  
Dose Measurement ◽  
Nuclear Power Plant Accident ◽  
Media Reports

This study analyzes data from telephone consultations made with a research institution during approximately one year following the March 11, 2011, Fukushima, Japan, Daiichi Nuclear Power Plant accident. Data was correlated with newspaper and online media coverage. During the analysis, many calls for consultation concerned aspects of daily life such as food, clothing, and housing and to radiation exposure during the accident. As the year of study went on, the proportion of consultation on daily life changed to more technical topics, such as dose measurement, scientific knowledge, natural radiation, and Russia’s Chernobyl accident. The topic of “children” raised the greatest number of consultations over the entire period; 20–40% of callers inquiring about soil, dose measurement and internal exposure asked also about children. Media reports on the topics consulted on were few except for those on dose measurement. The proportion of consultations on children and dose measurement may have been raised due to media reports circulating at about the same time. We concluded that it is important in postaccident risk communication that information related to daily living – especially protective measures that could be taken – and to effects on children be provided efficiently and at an appropriate timing.

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