INFLUENCE OF REFILL SOIL AND BUILDING MATERIAL EQUIVALENT DOSE RATE ON NEW NUCLEAR POWER PLANT SITES

2013 ◽  
Vol 13 (2) ◽  
pp. 259-264
Author(s):  
Vigilija Cidzikiene ◽  
Rasele Girgzdiene
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Dose Rate ◽  
Building Material ◽  
Nuclear Power ◽  
Equivalent Dose ◽  
Equivalent Dose Rate

scholarly journals Ecosystem model-based approach for modeling the dynamics of <sup>137</sup>Cs transfer to marine plankton populations: application to the western North Pacific Ocean after the Fukushima nuclear power plant accident

2016 ◽  
Vol 13 (2) ◽  
pp. 499-516 ◽  
Author(s):  
M. Belharet ◽  
C. Estournel ◽  
S. Charmasson
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Pacific Ocean ◽  
Dose Rate ◽  
North Pacific ◽  
Nuclear Power ◽  
Western North Pacific ◽  
North Pacific Ocean ◽  
Ecosystem Model ◽  
Western North Pacific Ocean

Abstract. Huge amounts of radionuclides, especially 137Cs, were released into the western North Pacific Ocean after the Fukushima nuclear power plant (FNPP) accident that occurred on 11 March 2011, resulting in contamination of the marine biota. In this study we developed a radioecological model to estimate 137Cs concentrations in phytoplankton and zooplankton populations representing the lower levels of the pelagic trophic chain. We coupled this model to a lower trophic level ecosystem model and an ocean circulation model to take into account the site-specific environmental conditions in the area. The different radioecological parameters of the model were estimated by calibration, and a sensitivity analysis to parameter uncertainties was carried out, showing a high sensitivity of the model results, especially to the 137Cs concentration in seawater, to the rates of accumulation from water and to the radionuclide assimilation efficiency for zooplankton. The results of the 137Cs concentrations in planktonic populations simulated in this study were then validated through comparison with the data available in the region after the accident. The model results have shown that the maximum concentrations in plankton after the accident were about 2 to 4 orders of magnitude higher than those observed before the accident, depending on the distance from FNPP. Finally, the maximum 137Cs absorbed dose rate for phyto- and zooplankton populations was estimated to be about 5  ×  10−2 µGy h−1, and was, therefore, lower than the predicted no-effect dose rate (PNEDR) value of 10 µGy h−1 defined in the ERICA assessment approach.

Natural variation of ambient dose rate in the air of Izu-Oshima Island after the Fukushima Daiichi Nuclear Power Plant accident

2015 ◽  
Vol 168 (4) ◽  
pp. 561-565 ◽  
Author(s):  
Fumihiko Maedera ◽  
Kazumasa Inoue ◽  
Masato Sugino ◽  
Ryosuke Sano ◽  
Mai Furue ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Dose Rate ◽  
Nuclear Power ◽  
Natural Variation ◽  
Nuclear Power Plant Accident ◽  
Fukushima Daiichi ◽  
Ambient Dose

scholarly journals V　Characteristics of Air Dose Rate Distribution in the Environment around the Fukushima Nuclear Power Plant site

RADIOISOTOPES ◽  
2015 ◽  
Vol 64 (9) ◽  
pp. 589-607
Author(s):  
Satoshi MIKAMI ◽  
Norihiro MATSUDA ◽  
Masaki ANDOH ◽  
Sakae KINASE ◽  
Mitsuaki KITANO ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Dose Rate ◽  
Nuclear Power ◽  
Rate Distribution ◽  
Plant Site

Estimation of the Dose Rate of Spent Fuel-Related Components of Lingao Nuclear Power Plant Using ORIGEN2 and MCNP5

2019 ◽  
Vol 24 (1) ◽  
pp. 64-70
Author(s):  
Mingliang Xie ◽  
Fei Xie ◽  
Fuchang Shan ◽  
Zhengquan Xie ◽  
Mingrui Li ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Dose Rate ◽  
Nuclear Power ◽  
Spent Fuel

Model of a Dry Storage Facility for a Medium Nuclear Power Plant

2001 ◽  
Author(s):  
Mile Bace ◽  
Kresimir Trontl ◽  
Dubravko Pevec
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Radiation Dose ◽  
Dose Rate ◽  
Nuclear Power ◽  
Storage Facility ◽  
Spent Fuel ◽  
Radiation Dose Rate ◽  
Dry Storage ◽  
Fuel Assemblies

Abstract The intention was to model a dry storage facility that could satisfy the needs of a medium nuclear power plant similar to the NPP Krsko. The attention has been focused on radiation dose rate analyses and criticality calculations. Using the SCALE 4.4 code package and modified QAD-CGGP code, we modeled a facility that satisfies the basic criteria for public radiation protection. The capacity of the storage is 1,400 spent fuel assemblies which is adequate for a forty years medium NPP lifetime.

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