Radiation Environment and Medicine (REM)

REM » Archives » REM Vol.9 No.2

Radiation Environment and Medicine Vol.9 No.2

  • Publisher : Hirosaki University press
  • Language : English
  • ISSN : 2423-9097 (PRINT), 2432-163X (ONLINE)
  • Release : August 2020
  • Issue : Hirosaki University Press
  • pp. 47-110

Articles

Review

Radiation Emergency Medicine Strategies Based on the Classification and Analysis of Nuclear and Radiological Emergencies

  • Seokki Cha1,2, Takakiyo Tsujiguchi3, Sang Tae Kim4, Young-woo Jin1,
    Changkyung Kim2 and Minsu Cho1*

  • 1Korea Institute of Radiological and Medical Science(KIRAMS), 75 Nowon-ro, Nowon-gu, Seoul, Republic of Korea
    2Hanyang University, STP(Science and Technology Policy) Program, 222 Wangsimni-ro, Seongdong-gu, Seoul, Republic of Korea
    3Hirosaki University Center for Radiation Support and Safety 66-1 Hon-cho, Hirosaki, Japan
    4Nuclear Safety and Security Commission, 178 Sejong-daero, Jongno-gu, Seoul, Republic of Korea

Abstract

Due to the unique nature of nuclear energy and radiation, nuclear disasters have radiation-based biological and psychological effects on both the immediate and over time effects. The radiation
effects on human beings can be deterministic, stochastic, and psychological. It is necessary to establish a strategy that can reasonably reduce these effects in nuclear and radiological
emergencies. For effective response, it is important to establish a phased resource utilization plans for radiation emergency medicine at national level. In this study, the definition of emergency
preparedness categories according to the international atomic energy agency publication was used to classify and analyze past nuclear and radiological emergencies. So we assumed scenarios using our classification and analysis results. And also radiation emergency medicine strategies should be arranged based on the roles of medical response institute during nuclear and radiological emergencies occured.

Review

Subtraction Computed Tomographic Angiography and Ultra-high-resolution Computed Tomography: New Era of Vascular Imaging

  • Ryoichi Tanaka*

  • Division of Dental Radiology, Department of Reconstructive Oral and Maxillofacial Surgery, Iwate Medical University, Iwate 028-3694, Japan
    Department of Radiology, Iwate Medical University, Iwate 028-3694, Japan

Abstract

Computed tomographic angiography (CTA) is a widely used noninvasive imaging technique for visualizing and evaluating vascular diseases. For global anatomical evaluation of vascular diseases,
CTA is superior to conventional catheter angiography because of its unlimited angulation in image projection. However, arterial calcification and/or vascular implants such as metallic stents could
hinder the evaluation of lesions inside. Additionally, the spatial resolution of CT is not small enough to evaluate peripheral vascular structures. Recent technical developments in CT allowed several new image processing techniques. The areas of technical developments are image subtraction and/or energy subtraction, which are used to detect fine luminal images. Another area of technical development is ultra-high-resolution CT, which has four times finer in-plane spatial resolution than conventional CT. There are other developments in image quality improvement and/or radiation dose reduction. Thus, new techniques and environments of CT allow finer vascular and structural imaging without invasiveness. In this review, the details of these techniques are described, and future insights are discussed.

Review

Estimating the Annual Average Dose to the Public from Ionizing Radiation in Ireland

  • Kevin Kelleher1*, Collette O’Connor1, Lorraine Currivan1, Noeleen Cunningham1, Mandy Lewis2, Stephanie Long1, Paul McGinnity3, Veronica Smith1 and Ciara McMahon1

  • 1Environmental Protection Agency, Regional Inspectorate Dublin, McCumiskey House, Richview, Dublin 14, Ireland
    2Health Service Executive, Dublin, Ireland
    3International Atomic Energy Agency, 4 Quai Antoine 1er, 98000 Monaco

Abstract

The public is constantly exposed to radiation from a variety of sources, both natural and artificial. Natural sources of radiation include cosmic radiation; external radiation from radioactivity in the
earth’s crust; the radioactive gases radon and thoron released from radioactivity in the earth’s crust; and radioactivity transferred to foodstuffs. There are also sources of artificial radioactivity in
the environment. The testing of nuclear weapons, nuclear accidents and authorised releases from nuclear facilities abroad have all resulted in radioactivity reaching Ireland. Radioactivity is also
released in small amounts into the Irish marine environment from hospitals and research facilities located along the Irish coastline. As with sources of natural radioactivity, artificial radioactivity
can give an external radiation exposure and also be transferred through the food chain to give an internal radiation exposure.
This work outlines the methodologies used to evaluate the dose received to members of the Irish public from the exposure pathways outlined above. The average annual effective dose to a
person in Ireland from all sources of radiation is now estimated as 4037 μSv. Natural sources of radioactivity account for 86% of the total effective dose in Ireland with the remainder attributed to
artificial sources and are dominated by radiation in medicine.

Regular Article

Environmental Monitoring of 134Cs and 137Cs Levels in Namie Town in 2018 and 2019

  • Miklós Hegedűs1, Thamaborn Ploykrathok1, Yoshitaka Shiroma1, 2, Kazuki Iwaoka1, 3, Ryohei Yamada1, 4, Takakiyo Tsujiguchi1, Masaru Yamaguchi1, Takahito Suzuki1, 5, Koya Ogura1, Yuki Tamakuma1, Hirofumi Tazoe1, Naofumi Akata1, Masahiro Hosoda1, Ikuo Kashiwakura1 and Shinji Tokonami1*

  • 1Hirosaki University, Hon-cho 66-1, 036-8564 Hirosaki, Japan
    2University of the Ryukyus, 1 Senbaru, Nishihara-cho Okinawa 903-0213, Japan
    3National Institutes for Quantum and Radiological Sciences and Technology, 4-9-1 Anagawa, Inage, Chiba 263-8555, Japan
    4Japan Atomic Energy Agency, 4-33 Muramatsu, Tokai, Ibaraki, 319-1194, Japan
    5Fuji Electric Co., Ltd. 1 Fuji-cho, Hino-shi, Tokyo 191-8502, Japan

Abstract

The Fukushima Dai-ichi Nuclear Power Plant accident caused a release of radionuclides covering a significant area in Fukushima Prefecture, Japan. In the current work the radio-caesium
concentrations observed in some points of Namie Town between 2018. June. and 2019. September in river water, river sediment and aerosol are being presented. The observed concentrations were up to 205.9 ± 9 mBq/L for 137Cs in unfiltered water and less than 4000 μBq/m3 for 137Cs in air, while the sediment had a maximum of 4041 ± 2 Bq/kg-dry for 137Cs. In many cases the water and aerosol samples had activity concentrations below the detection limit. These values decreased compared to the year 2017 for the same area. The potential yearly committed effective doses were estimated based on the data, with the calculated annual dose rates being well below any regulatory limit.

Note

Dose Assessment of Radium-226 in Drinking Water from Mamuju, a High Background Radiation Area of Indonesia

  • Eka Djatnika Nugraha1, 2, Masahiro Hosoda2, 3, Kusdiana1, Ilma D Winarni1, Ariska Prihantoro1, Takahito Suzuki2, Yuki Tamakuma2, 3, Naofumi Akata3 and Shinji Tokonami3*

  • 1Center for Technology of Radiation Safety and Metrology, National Nuclear Energy Agency of Indonesia,
    Jl. Lebak Bulus Raya No 49, Jakarta, 12440, Indonesia
    2Department of Radiation Science, Graduate School of Health Sciences, Hirosaki University,
    66-1 Hon-cho, Hirosaki, Aomori 036-8564, Japan
    3Institute of Radiation Emergency Medicine, Hirosaki University, 66-1 Hon-cho, Hirosaki, Aomori 036-8564, Japan

Abstract

Mamuju is an area of Indonesia with high radiation exposure compared to the average across the country. It is included in the high background radiation area (HBRA) category. Radium-226
(226Ra) is one of the natural radionuclides that, if contained in drinking water, can be harmful to human health. Mamuju’s residents generally use well water for their daily needs. Radium-226 is
easily soluble in water and emits alpha particles. Therefore, measurement of 226Ra in drinking water is necessary to protect the public from radiation. A total of 13 drinking water samples were
obtained from the HBRA in Mamuju. They had a concentration range of 14–238 mBq L-1. These concentrations are below the World Health Organization recommendation, which is 1 Bq L-1, with an annual effective dose (mSv y-1) from the ingestion of 226Ra in water ranging between 3–49 μSv.

Note

An Alternative Approach to Background Radiation Monitoring Using Smartphone-coupled Personal Dosimeter POLISMART in Shimokita Peninsula, Japan

  • Valerie Swee Ting Goh1, Yaeko Yamamoto2, Yasushi Mariya3, 4, Toshiya Nakamura1, Andrzej Wojcik5, Shinji Tokonami6 and Tomisato Miura1, 7*

  • 1Department of Bioscience and Laboratory Medicine, Hirosaki University Graduate School of Health Sciences,
    66-1 Hon-cho, Hirosaki, Aomori 036-8564, Japan
    2Community General Support Center, 17-2 Sato, Sunakomata, Higashidori, Aomori 039-4222, Japan
    3Department of Radiology/Radiation Oncology, Mutsu General Hospital, 1 -2-8 Kogawamachi, Mutsu, Aomori 035-8601, Japan
    4Department of Radiation Oncology, Aomori Rosai Hospital, 1 Minamigaoka, Shirogane-cho,
    Hachinohe 031-8551, Japan (Current affiliation)
    5Department of Molecular Biosciences, The Wenner-Gren Institute, Stockholm University,
    Svante Arrhenius väg 20C, Stockholm 114 18, Sweden
    6Department of Radiation Physics, Institute of Radiation Emergency Medicine, Hirosaki University,
    66-1 Hon-cho, Hirosaki, Aomori 036-8564, Japan
    7Department of Risk Analysis and Biodosimetry, Institute of Radiation Emergency Medicine, Hirosaki University,
    66-1 Hon-cho, Hirosaki, Aomori 036-8564, Japan

Abstract

Since the Fukushima Dai-ichi Nuclear Power Plant accident in 2011, background radiation dose monitoring was increased throughout Japan for public assurance. In Shimokita Peninsula of Aomori
Prefecture, several nuclear-related facilities are present. Background radiation monitoring data within nuclear facilities or selected residential areas in larger cities, measured by nuclear facilities or government agencies, is publicly available. To increase public involvement in radiation monitoring and encourage communication during non-emergency periods, a regional radiation monitoring project in places involved in radiation emergency response was launched in 2015. Background dose rate monitoring using personal dosimeter PM1904A POLISMART® II of four healthcare facilities and one municipal city office in Mutsu City and Higashidori Village determined the baseline level of outdoor background radiation from 2015 to 2018, which was an average of 0.0499 ± 0.011 μSv/h. Temperature, humidity, wind speed, accumulated snow and precipitation did not significantly affect dose rates measured with POLISMART. Although background dose rates measured by POLISMART were higher than those measured by monitoring posts and other detectors in similar locations and measurement periods, annual background radiation calculated from POLISMART measurements was lower than Japan’s estimated average of 0.7 mSv/yr. From these results, POLISMART may be additionally used for environmental radiation monitoring and public education.

Note

Low-volume Electrolytic Enrichment for Tritium Measurement Using Improved Solid Polymer Electrolyte System at NIFS and Its Application

  • Naofumi Akata1, 2*, Chie Iwata3, Akemi Kato3, Masahiro Tanaka3, Hirofumi Tazoe1, Nagayoshi Shima4, Kimpei Ichiyanagi5, Miklós Hegedűs6, Gergő Bátor2, Tibor Kovács2 and Hideki Kakiuchi7

  • 1Radiation Chemistry Department, Institute of Radiation Emergency Medicine, Hirosaki University;
    66-1 Hon-cho, Hirosaki, Aomori 036-8564, Japan
    2Institute of Radiochemistry and Radioecology, University of Pannonia, H-8201 Veszprém, P.O.B.: 158, Hungary.
    3National Institute for Fusion Science, National Institute of Natural Sciences; 322-6 Oroshi-cho, Toki, Gifu 509-5292, Japan
    4Kyushu Environmrntal Evaluation Association; 1-10-1 Matsukadai, Higashi-ku, Fukuoka 813-0004 Japan
    5Kumamoto University; Kurokami 2-39-1, Chuo-ku, Kumamoto, 860-8555, Japan
    6Radiation Physics Department, Institute of Radiation Emergency Medicine, Hirosaki University;
    66-1 Hon-cho, Hirosaki, Aomori 036-8564, Japan
    7Department of Radioecology, Institute for Environmental Sciences; 1-7 Ienomae, Obuchi, Rokkasho, Aomori 039-3212 Japan

Abstract

We evaluated the enrichment factor of tritium for an improved solid polymer electrolyte (SPE) system. In this system, water sample reservoirs were made of double-glazed glass, and cooling
water was circulated in the double glass to cool the sample. As the result, a tritium enrichment factor of 5.00 was obtained and the MDL of tritium measurement with a low-background
liquid scintillation counter coupled to this improved enrichment process was determined to be approximately 0.062 Bq L-1. Tritium concentration in monthly precipitation at Kumamoto was
measured using this method combining a low-background liquid scintillation counter and this improved SPE system.

Note

A Comparative Study of the Outdoor Absorbed Dose Rate in Air by In-situ and Soil-sampling-based Measurement Methods

  • Chutima Kranrod1, 2*, Supitcha Chanyotha2, Phongphaeth Pengvanich2, Rawiwan Kritsananuwat2, Masahiro Hosoda1, 3 and Shinji Tokonami1

  • 1Institute of Radiation Emergency Medicine, Hirosaki University, Hirosaki, Aomori 036-8564, Japan.
    2Natural Radiation Survey and Analysis Research Unit, Department of Nuclear Engineering,
    Faculty of Engineering, Chulalongkorn University, Bangkok 10330, Thailand
    3Hirosaki University Graduate School of Health Sciences, Hirosaki, Aomori 036-8564, Japan

Abstract

Outdoor absorbed dose rates in air were evaluated in the environs of Eastern, Western, and Southern Thailand using the gamma-ray pulse height distribution obtained by in-situ NaI(Tl)
scintillation spectrometer, and by analyses of soil samples for 226Ra, 232Th, and 40K activity concentration using an HPGe gamma spectrometry. The geometric mean values of the outdoor
gamma dose rates from the direct measurements and the soil analyses were 45 ± 8 nGy/h and 69 ± 3 nGy/h respectively. The ratio of the average absorbed dose rate in air inferred from the activity concentrations of radionuclides in soil to the average absorbed dose rate in air from the in-situ measurement in this study is 1.5.

Report

Development of the System of Radiological Protection and Medical Exposure: Basic Information and Trends

  • Michiya Sasaki1* and Toshioh Fujibuchi2

  • 1Radiation Safety Research Center, Nuclear Technology Research Laboratory, Central Research Institute of Electric Power Industry
    2-11-1 Iwado kita, Komae-shi, Tokyo 201-8511, Japan
    2Division of Quantum Radiation Sciences, Department of Health Sciences, Faculty of Medical Sciences, Kyushu University
    3-1-1 Maidashi, Higashi-ku, Fukuoka-shi, Fukuoka 812-8582, Japan

Abstract

The International Commission on Radiological Protection (ICRP) is a community of more than 250 globally-recognised experts in radiological protection science, policy, and practice from more
than 30 countries, and is also a charity. The objective of the system of radiological protection is to provide an appropriate level of protection for people and the environment against the harmful
effects of radiation exposure without unduly limiting the individual or societal benefits of activities involving radiation. This article briefly overviews the history of ICRP, the development of the
system of radiological protection, and the recent trends of its publications, especially from the viewpoint of medicine.

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