INVESTIGATION OF EXTERNAL RADIATION DOSES DURING RESIDENTS’ TEMPORAL STAY TO NAMIE TOWN, FUKUSHIMA PREFECTURE

2019 ◽  
Vol 184 (3-4) ◽  
pp. 514-517 ◽  
Author(s):  
T Tsujiguchi ◽  
Y Shiroma ◽  
T Suzuki ◽  
Y Tamakuma ◽  
M Yamaguchi ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Radiation Doses ◽  
External Radiation ◽  
Dose Equivalent ◽  
Fukushima Prefecture ◽  
Maximum Value ◽  
External Radiation Dose ◽  
Equivalent Rate ◽  
The Relationship ◽  
The Town

Abstract Namie Town in Fukushima Prefecture, the majority of which was an evacuation area as a result of the effects of the Fukushima Daiichi Nuclear Power Plant accident, carried out a ‘temporal stay’ in September 2016 so that residents could check their houses. Therefore, in cooperation with the town authorities, the authors distributed personal dosemeters and behaviour record forms to record the personal dose equivalent rate and investigate the relationship between residents’ external radiation dose and their behaviour. When the personal dose equivalent rate was calculated from the measured personal dose equivalent per hour, the median was 0.12 μSv h−1, the maximum value and the minimum value were 0.58 and 0.06 μSv h−1, respectively. Meanwhile, since personal fluctuations were observed in personal dose equivalent, grasping the relationship between residents’ behaviour and exposed dose can be applied to risk communication.

Correction Coefficients for Measuring the Ambient Dose Equivalent Rate of Neutrons

ANRI ◽  
2021 ◽  
Vol 0 (4) ◽  
pp. 32-40
Author(s):  
Alexander Alexeev ◽  
Vladimir Pikalov ◽  
Pavel Alexeev
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Dose Equivalent ◽  
Equivalent Rate ◽  
Ambient Dose Equivalent ◽  
Ambient Dose

Calculations of the response for the most widely used neutron dosimeters at the Russian nuclear power plant (NPP) have been performed. It is shown that in some cases it is necessary to introduce a correction for the measured value of the ambient dose equivalent rate (AEDR). The experimentally tested values of the correction for measuring AEDR in the containment rooms of NPP with VVER-1200 are given.

Assessment of the Public Radiation Protection and Economic Activity Safety in the Area of the Developed Uranium Deposit

2020 ◽  
Vol 65 (2) ◽  
pp. 11-16
Author(s):  
A. Titov ◽  
N. Shandala ◽  
D. Isaev ◽  
M. Semenova ◽  
V. Seregin ◽  
...  
Keyword(s):  
Economic Activity ◽  
Equilibrium Concentration ◽  
Dose Equivalent ◽  
Economic Activities ◽  
The Public ◽  
Equivalent Rate ◽  
Ambient Dose Equivalent ◽  
Equilibrium Concentrations ◽  
Effective Doses ◽  
The Town

Purpose: To analize radiation situation in the vicinity of mine number one of the Lermontov Production Association “Almaz” in the areas of the public residence and economic activities. Material and methods: During the study, methods of pedestrian gamma surveys with a portable spectrometric complex MKS-01A “Multirad-M” and short-term measurements of radon equivalent equilibrium concentration with aerosol alpha radiometer RAA-20P2 “Poisk” were used. Results: Along the main roads used by the population for walks and rest, the values of the gamma ambient dose equivalent rate vary within the range between 0.10 and 0.86 μSv/h. Local areas with excess of the remediation criterion (0.6 μSv / h), established by the Sanitary Rules for elimination, conservation and changing functions of facilities for radioactive ore mining and milling (SP LKP-91), are located on the ascent of Beshtau Mountain from the side of the Town of Pyatigorsk (near tunnels and dumps). Along other routes, the remediation criteria are met. External effective doses to the population in a single passage of the routes vary from 1.0 to 1.6 µSv. The highest contribution to the dose from manmade radiation does not exceed 30 %. The highest external doses (4.3 μSv at the contribution of manmade radiation about 70 %) can be realized when resting near the most contaminated parts of the dumps or tunnel mouths. The equivalent equilibrium concentrations of radon progenies in air along the routes did not exceed 60 Bq/m3. The effective internal dose due to inhalation intake of radon and its progenies will not exceed 3 μSv when single passing routes. Conclusions: In the main areas of the residence and economic activity of the population in the vicinity of mine number 1 , the radiation situation at some locations does not comply with the requirements of the SP LKP-9, however, it does not pose a threat to public health.

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