• Proceedings of the Korea Air Pollution Research Association Conference
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• 2003.05b
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• pp.67-68
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• 2003

라돈은 일반적으로 가장 잘 알려진 천연 방사성핵종 중 하나로서 무향 무색의 불활성기체이며 붕괴과정에서 알파입자를 방출한다. 라돈에 의한 피폭선량은 라돈붕괴에 의해 생성된 라돈자손이 호흡기관 표면에 침착되어 방출하는 알파선에 기인한다. 따라서, 피폭선량에 주로 기인하는 것은 라돈 자신이 아니라 그의 단 반감기 라돈자손들이다. 이처럼 라돈은 잘 알려진 폐암 유발원으로서 고농도의 라돈에 장기간 노출되는 경우 폐암을 유발할 수 있다. UNSCEAR 보고서(1993)는 자연 환경중에서 인간이 받는 연간 총 피폭선량인 2.4 mSv중 약 50%에 해당하는 1.15 mSv가 라돈과 그 자손에 의한 것이며 대부분 옥내에서의 호흡에 의해 비롯된다고 평가하고 있다. (중략)

• Journal of the Korea Convergence Society
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• v.8 no.8
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• pp.147-154
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• 2017

The purpose of this study is to calculate and compare administered activities(MBq) and effective dose(mSv) of the various pediatric dose formulas of pediatric nuclear medicine and to provide base data for the criteria of the optimal administered activities. This study compares dosages and effective doses of 5 types of pediatric dose formulas(Clark rule, Area rule, Webster rule, Young rule, Solomon(Fried) rule) based on the dosage for adults of 2 types of radiopharmaceuticals($^{99m}Tc$-MDP, $^{99m}Tc$-Pertechnetate). The administered activities in adults, which is the criteria for calculating the Pediatric administered activities, used the value from the 'Nuclear Medicine' written by J-G Jeong & M-Ch Lee. and the administered activities by the radioactivity per effective dose(mSv/MBq) of the radiopharmaceuticals for calculating the effective dose used the value from ICRP 80 and the UNSCEAR 2008 Report. As a result of the study, the output of Young rule is the lowest, and its difference between other formulas is from minimum 1.7 times to maximum 3,4 times. The difference between administered activities of $^{99m}Tc$-MDP is maximum 309.9MBq and the effective dose is 3.76mSv. $^{99m}Tc$-Pertechnetate showed the figure at the maximum 154.9MBq and the effective dose has a difference of 5.50mSv. Since the pediatric dose formulas differ not only in administered activities but also in effective doses, the optimal administered activities have to be developed for optimization of medical radiation.

• Journal of radiological science and technology
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• v.32 no.2
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• pp.219-224
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• 2009

We investigated the amounts of radiation exposure from $^{238}U$, $^{232}Th$, and $^{40}K$ which are three major radionuclides naturally residing in soil of the Korean peninsula. The experimental results showed that the concentrations of the radionuclides were 15.77$\pm$7.27, 290.05$\pm$73.92 and 750.30$\pm$165.38 Bq/kg respectively. The absorbed dose rate based on the measured concentrations was 213.76$\pm$46.37 nGy/hr, while the spatial gamma absorbed dose rate measured in the same region was 123.90$\pm$19.18 nGy/hr. The effective dose rate was 0.26 mSv/yr, which is significantly higher than the world average effective dose rate 0.07 mSv/yr provided by the UNSCEAR.

• Journal of Radiation Protection and Research
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• v.32 no.3
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• pp.97-104
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• 2007

The corelation between the indoor volume and the measured radon concentration has been analyzed by comparing the radon concentration and the indoor volume of apartment rooms in Jeonju City. We also measured the annual exposure dose based on the variation in indoor radon concentration over time. To do this, we took 8 larger rooms and 8 smaller rooms of apartment, respectively, as a sample. The average volume of the larger rooms and that of the smaller rooms were $31.59\;m^3$ and $16.82\;m^3$, respectively. The average radon concentration of the larger rooms and that of the smaller rooms turned out to be $71.73\;Bq/m^3$ and $108.51\;Eq/m^3$, respectively. indicating that indoor volume is in inverse proportion to the radon concentration, i.e., the bigger the ratio of the surface area/volume, the higher the indoor radon concentration. From the measurement of the variation in indoor radon concentration over time fur a single day, the average intraday radon concentration variation was found to be about $46.8\;Bq/m^3$. The highest level of concentration ($114.5\;Bq/m^3$) was measured between 8 and 10 AM and the lowest level of concentration ($67.7\;Bq/m^3$) between 2 and 4 PM. The annual exposure dose turned out to be in the range of 0.3 mSv/yr to 2.16 mSv/yr, showing that the dose in some apartments exceeded 1.3 mSv/yr, the numerical value presented by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR).

• Journal of Radiation Protection and Research
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• v.42 no.2
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• pp.114-129
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• 2017

Background: The purpose of this paper is to confirm the event timings and the magnitude of fission product aerosol release from the Fukushima accident. Over a few hundreds of technical papers have been published on the environmental impact of Fukushima Daiichi accident since the accident occurred on March 11, 2011. However, most of the research used reverse or inverse method based on the monitoring of activities in the remote places and only few papers attempted to estimate the release of fission products from individual reactor core or from individual spent fuel pool. Severe accident analysis code can be used to estimate the radioactive release from which reactor core and from which radionuclide the peaks in monitoring points can be generated. Materials and Methods: The basic material used for this study are the initial core inventory obtained from the report JAEA-Data/Code 2012-018 and the given accident scenarios provided by Japanese Government or Tokyo Electric Power Company (TEPCO) in official reports. In this research a forward method using severe accident progression code is used as it might be useful for justifying the results of reverse or inverse method or vice versa. Results and Discussion: The release timing and amounts to the environment are estimated for volatile radioactive fission products such as noble gases, cesium, iodine, and tellurium up to 184 hours (about 7.7 days) after earthquake occurs. The in-plant fission product behaviors and release characteristics to environment are estimated using the severe accident progression analysis code, MELCOR, for Fukushima Daiichi accident. These results are compared with other research results which are summarized in UNSCEAR 2013 Report and other technical papers. Also it may provide the physically based arguments for justifying or suspecting the rationale for the scenarios provided in open literature. Conclusion: The estimated results by MELCOR code simulation of this study indicate that the release amount of volatile fission products to environment from Units 1, 2, and 3 cores is well within the range estimated by the reverse or inverse method, which are summarized in UNSCEAR 2013 report. But this does not necessarily mean that these two approaches are consistent.

• Journal of Radiation Protection and Research
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• v.47 no.1
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• pp.16-21
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• 2022

Background: Epidemiological observations such as mental retardation, physical deformities, etc., in children besides different types of cancer in the adult population of the Malwa region have been reported. The present study is designed to get insight into the role of naturally occurring radioactive material (NORM) in causing detrimental health effects observed in the general population of this region. Materials and Methods: Deep soil samples were collected from different locations in the Malwa region. Their activity concentrations were determined using low-level background gammaray spectrometry. High efficiency and high purity germanium detector capped in a lead-shielded chamber having a resolution of 1.8 keV at 1,173 keV and 2.0 keV at the 1,332 keV line of ⁶⁰Co was used in the present work. Data were evaluated with Genie-2000 software. Results and Discussion: Mean activity concentrations of ²³⁸U, ²³²Th, and ⁴⁰K in deep soil were found to be 101.3 Bq/kg, 65.8 Bq/kg, and 688.6 Bq/kg, respectively. The mean activity concentration of ²³⁸U was found to be three and half times higher than the global average prescribed by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). It was further observed that the activity concentration of ²³²Th and ⁴⁰K has a magnitude that is nearly one and half times higher than the global average prescribed by UNSCEAR. In addition, the radioisotope ¹³⁷Cs which is likely to have its origin in radiation fallout was also observed. It is postulated that the NORM present in high quantity in deep soil somehow get mobilized into the water aquifers used by the general population and thereby causing harmful health problems. Conclusion: It can be stated that the present work has been able to demonstrate the use of low background gamma-ray spectrometry to understand the role of NORM in causing health-related effects in a general population of the Malwa region of Punjab, India.

• Nuclear Engineering and Technology
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• v.52 no.6
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• pp.1282-1288
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• 2020

In the first study, the Radon emanation and radiological hazards associated with radionuclides in soil samples, collected from 9 various date palm farms located in 3 different districts in Saudi Arabia were determined through a high purity Germanium (HPGe) gamma-ray spectrometer. The estimated average values of Radon emanation coefficient and Radon mass exhalation rate for soil samples were 0.535 ± 0.016 and 50.063 ± 7.901 mBqkg^-1h^-1, respectively. The annual effective dose of radionuclides in all sampling locations was found to be lower than UNSCEAR's recommended level of 0.07 mSvy^-1 for soil in an outdoor environment. In the secondary study, gross α and gross β activities in soil and date palm pits samples were measured by a low background α/β counting system. Average values of gross α and gross β activities in soil and date palm pits samples were 5.761 ± 0.360 Bqkg^-1, 38.219 ± 8.619 Bqkg^-1 and 0.556 ± 0.142 Bqkg^-1, 24.266 ± 1.711 Bqkg^-1, respectively.

• Journal of Environmental Health Sciences
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• v.33 no.4
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• pp.264-275
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• 2007

The objective of this study was to offer basic and scientific data for decision-making of policy for improvement and management of radon, natural radiation gas, in Korea and to form the foundation of radon related international cooperation. Therefore, this study collected and re-analysed the articles on exposure of radon in various indoor environment in journals related environment in Korea since 1980 and estimated the annual exposure dose and effective dose by exposure of radon received by inhabitants in them. The highest pooled average radon concentration of $50.17{\pm}4.08\;Bq/m^3$ (95% CI : $42.17{\sim}58.17\;Bq/m^3$) was found in dwelling house among various indoor environment. All of pooled average radon concentration estimated in this study showed lower than the guideline concentration ($148\;Bq/m^3)$ of US EPA and the Korean Ministry of Environment. The annual effective dose received by inhabitants in various indoor environment was estimated 1.071 mSv/yr. That is equal to annual effective dose (1.0 mSv/yr) by exposure of radon estimated by UNSCEAR.

• Journal of Korean Society of Occupational and Environmental Hygiene
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• v.26 no.2
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• pp.109-118
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• 2016

Objectives: To review reference levels by the international and domestic management and provide the basis for setting occupational exposure limits(OELs) of radon in Korea Methods: Government's organizations with laws and systems for monitoring radon exposure were investigated and compared. There are five laws governing Indoor Air Quality(IAQ) control such as Occupational Safety and Health Act, Indoor Air Quality Control in Public Use Facilities, Etc. Act, School Health Act, Public Health Control Act and Parking Lot Act in Korea. It was surveyed that a total of 32 countries including 24 countries in the European Union(EU), six countries in Asian and two countries in North America setting the reference levels for radon in the world. Results: In Korea, there are set guidelines for radon in the Ministry of Environment and the Ministry of Education. Reference levels of radon for existing dwellings were $150{\sim}400Bq/m^3$ for Western European countries, and $200{\sim}1,500Bq/m^3$ in Eastern European countries. Approximately 67% of those EU countries were set up $400Bq/m^3$ to the standards for existing dwellings. EU countries such as Luxembourg, Finland, Norway, Sweden and Russia had adopted mandatory level for radon. Radon guidelines for new dwellings were set more strictly reference level($200Bq/m^3$) than existing dwellings. Conclusions: International organizations such as ICRP, UNSCEAR and NCRP, etc. had recommended the guidelines for radon. It was calculated the relation of the dose conversion factors with the annual effective doses. the OELs of radon suggest to need to establish $150Bq/m^3$ for office room and $400{\sim}1,000Bq/m^3$ for the workplace.

• Journal of Radiation Protection and Research
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• v.23 no.3
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• pp.185-196
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• 1998

현재의 방사선방호 원칙과 체계는 국제방사선방호위원회 (ICRP)의 권고에 기반을 두고 있 다. ICRP 의 권고는 대부분 히로시마/나카사키 원폭피해 생존자들에 대한 역학조사 및 수명 연구결과 그리고 관련 방사선생물학 연구결과를 바탕으로 전세계 5개 인구집단(일본, 미국, 푸에리토리코, 영국과 중국)에 대한 방사선위험계수의 예측 및 평가결과에 근거를 두고 있다. 이 저선량 방사선의 (확률적 영향) 위험계수는 인체피폭 방사선량과 그 영향간에는 선형 비례관계가 있으며 영향유발의 문턱값이 존재하지 않는다는 가정인 '선형 무문턱값 선량-영향 모델 (Linear No-Threshold Dose-Effect Model, 이른바 LNT 모텔)' 을 도입하여 유도된 것이다(譯者 밑줄). 그러나 이 LNT 가정의 과학적 근거와 정당성에 대한 비난이 원자력산업계나 일부 과학자들에 의해 제기된 이래, 최근에는 미국 보건물리학회 (HPS)에서 'LNT 가정이 선량과 영향의 관계를 단순화하며 낮은 선량의 위험음 과대평가한다'는 성명서를 발표하기도 했다. 이후 이에 대한 논쟁이 다시 시작되어, 1997 년에 스페인의 Sevill에서는 IAEA와 WHO의 공동주최와 UNSCEAR의 협조로 '저준위 방사선 영향에 대한 국제회의'가 개최되기도 하였으나 아직 어느 쪽에도 유리한 결론이 단정적으로 나지 않았으며, 실질적인 대안이 없는 현실에서 이 LNT 가정은 여전히 방사선방호의 철학적 기초로 남아 있다(譯者 밑줄). 한편, 저선량 방사선의 영향에 대해서는 우리나라에서도 '방사선방어학회, ‘98 년 춘계 심포지움' 및 '원자력학회, '98 년 춘계 학술발표회 워크??????'에서 한양대학교의 이재기 교수에 의하여 소개, 논의된 바 있다.이 논문은 이러한 논의의 후속으로 역자중 일인이 위원으로 있는 OECD/NEA 방사선방호위원회 (CRPPH)가 최근에 ('98.7.) 발간한 보고서를 번역, 주해한 것으로, 과학지식의 진보에 따라 방사선방호분야에서 관심이 되는 주제들에 대한 위원회의 검토의견을 소개하고 있다. 따라서 이 논문이 국내의 방사선방호분야 관계자들에게 최신정보 습득과 지식함양에 좋은 도움이 되기를 기대한다.