scholarly journals Fluctuation Factors of Ambient Dose Rates in the Vicinity of Hamaoka Nuclear Power Plant

RADIOISOTOPES ◽  
2004 ◽  
Vol 53 (7) ◽  
pp. 405-413 ◽  
Author(s):  
Hideyuki YOSHIDA ◽  
Masahiro AIKA ◽  
Akio IKI ◽  
Yuko IBUKI ◽  
Rensuke GOTO
2016 ◽  
Vol 45 (2_suppl) ◽  
pp. 71-77 ◽  
Author(s):  
S. Endo

The residents of Suetsugi in Fukushima Prefecture measured ambient dose rates and radiocaesium concentrations in the soil after the accident at Fukushima Daiichi nuclear power plant in an attempt to maintain living conditions in the region. The measurements were colour plotted into maps to visualise the contamination. Through the receipt of external support, a number of radioactivity-related initiatives were implemented for the residents. Studies were also undertaken regarding the impact of radiocaesium contamination on rice farming in Suetsugi following the Great East Japan Earthquake and the accident at Fukushima Daiichi nuclear power plant.


2015 ◽  
Vol 168 (4) ◽  
pp. 561-565 ◽  
Author(s):  
Fumihiko Maedera ◽  
Kazumasa Inoue ◽  
Masato Sugino ◽  
Ryosuke Sano ◽  
Mai Furue ◽  
...  

ANRI ◽  
2021 ◽  
Vol 0 (4) ◽  
pp. 32-40
Author(s):  
Alexander Alexeev ◽  
Vladimir Pikalov ◽  
Pavel Alexeev

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.


2016 ◽  
Vol 158-159 ◽  
pp. 1-8 ◽  
Author(s):  
Kazumasa Inoue ◽  
Hiroshi Tsuruoka ◽  
Tan Van Le ◽  
Moeko Arai ◽  
Kyoko Saito ◽  
...  

2014 ◽  
Vol 111 (10) ◽  
pp. E914-E923 ◽  
Author(s):  
Kouji H. Harada ◽  
Tamon Niisoe ◽  
Mie Imanaka ◽  
Tomoyuki Takahashi ◽  
Katsumi Amako ◽  
...  

Radiation dose rates were evaluated in three areas neighboring a restricted area within a 20- to 50-km radius of the Fukushima Daiichi Nuclear Power Plant in August–September 2012 and projected to 2022 and 2062. Study participants wore personal dosimeters measuring external dose equivalents, almost entirely from deposited radionuclides (groundshine). External dose rate equivalents owing to the accident averaged 1.03, 2.75, and 1.66 mSv/y in the village of Kawauchi, the Tamano area of Soma, and the Haramachi area of Minamisoma, respectively. Internal dose rates estimated from dietary intake of radiocesium averaged 0.0058, 0.019, and 0.0088 mSv/y in Kawauchi, Tamano, and Haramachi, respectively. Dose rates from inhalation of resuspended radiocesium were lower than 0.001 mSv/y. In 2012, the average annual doses from radiocesium were close to the average background radiation exposure (2 mSv/y) in Japan. Accounting only for the physical decay of radiocesium, mean annual dose rates in 2022 were estimated as 0.31, 0.87, and 0.53 mSv/y in Kawauchi, Tamano, and Haramachi, respectively. The simple and conservative estimates are comparable with variations in the background dose, and unlikely to exceed the ordinary permissible dose rate (1 mSv/y) for the majority of the Fukushima population. Health risk assessment indicates that post-2012 doses will increase lifetime solid cancer, leukemia, and breast cancer incidences by 1.06%, 0.03% and 0.28% respectively, in Tamano. This assessment was derived from short-term observation with uncertainties and did not evaluate the first-year dose and radioiodine exposure. Nevertheless, this estimate provides perspective on the long-term radiation exposure levels in the three regions.


Author(s):  
Davor Grgic ◽  
Mario Matijevic ◽  
Paulina Duckic ◽  
Radomir Jecmenica

Abstract In this paper shielding analysis was performed to determine neutron and gamma dose rates around the transfer cask HI-TRAC VW loaded with Spent Fuel Assemblies (SFA) from Nuclear Power Plant (NPP) Krsko Spent Fuel Dry Storage (SFDS) Campaign one. The HI-TRAC VW is a multi-layered cylindrical vessel designed to accept a Multi Purpose Canister (MPC) during loading, unloading and transfer to dry storage building. The MPC can contain up to 37 spent fuel assemblies. The analysis was divided into two steps. The first step was the source term generation using ORIGEN-S module of the SCALE code package. The source was calculated based on the operating history of spent fuel assemblies currently located in the NPP Krsko spent fuel pool. The obtained particle intensities and source spectra of the SFA were used in the second step to calculate the dose rates around the transfer cask. A comprehensive hybrid shielding analysis included the calculation of dose rates resulting from fuel neutrons and gammas, neutron induced gammas (n-g reaction), and hardware activation gammas under normal conditions and during accident scenario. To obtain the dose rates within the acceptable uncertainties, FW-CADIS variance reduction scheme, as implemented in ADVANTG code, was adopted for accelerating final MCNP6 calculations. The dose rates around HI-TRAC VW cask were calculated using MCNP6 code for all 16 casks loading belonging to Campaign one in order to illustrate the impact of fuel assembly selection schemes proposed by company responsible for project realization (Holtec International).


Sign in / Sign up

Export Citation Format

Share Document