• Title/Summary/Keyword: System of radiation protection

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A Preliminary Establishment of Dose Constraints for the Member of Public Taking into Account Multi-unit Nuclear Power Plants in Korea (국내 복수호기 원전 운영을 고려한 일반인 선량제약치 설정에 대한 고찰)

  • Kong, Tae-Young;Choi, Jong-Rack;Son, Jung-Kwon;Kim, Hee-Geun
    • Journal of Radiation Protection and Research
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    • v.37 no.3
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    • pp.129-137
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    • 2012
  • In the 2007 recommendation, the ICRP evolves from the previous process-based system of practices and intervention to the system based on the characteristics of radiation exposure situation. In addition, ICRP recommends the application of source-related dose constraints under the planned exposure situation as a tool for the optimization of protection to workers and the member of public. In this study, the analysis of radioactive effluents from Korean nuclear power plants and the public dose assessment were conducted in reference with the use of dose constraints. Finally, the measure to implement the dose constraints for the member of public was suggested taking into account multi-unit reactors operating at a single site in Korea.

A Comparision of Mghr Prescription to Doses at Ponts A and B in Intracavitary Radiotherapy of Cervix Cancer (자궁경구암(子宮頸口癌) 강내조사치료시(腔內照射治療時) A점(點) B점(點) 선량계산방법(線量計算方法)과 mghr 단위(單位) 방법(方法)의 비교(比較))

  • Park, Charn-Il;Ha, Sung-Whan;Kang, Wee-Saing
    • Journal of Radiation Protection and Research
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    • v.6 no.1
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    • pp.31-33
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    • 1981
  • The 42 patients with carcinoma of the cervix, performed intracavitary radiotherapy, were analysed the doses at points A and B comparing to the mghr prescription. The doses at points A and B were calculated by PC-12 computer planning system. Correlation coefficienty between doses at points A and B and the mghr prescription are 0.82 (p<0.001) and 0.90 (p<0.001) respectively. The slope of the point A line is 0.70 and the slope of the point B is 0.21. Therefore, the dose at point A is approximately 3/4 the mghr prescription and the dose at point B is approximately 1/4 the mghr precription.

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Assessment of Radiological Hazards in Some Foods Products Consumed by the Malian Population Using Gamma Spectrometry

  • Adama Coulibaly;David O. Kpeglo;Emmanuel O. Darko
    • Journal of Radiation Protection and Research
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    • v.48 no.2
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    • pp.84-89
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    • 2023
  • Background: Food consumption is one of the most important routes for radionuclide intake for the public; therefore, there is the need to have a comprehensive understanding of the amount of radioactivity in food products. Consumption of radionuclide-contaminated food could increase potential health risks associated with exposure to radiation such as cancers. The present study aims to determine radioactivity levels in some food products (milk, rice, sugar, and wheat flour) consumed in Mali and to evaluate the radiological effect on the public health from these radionuclides. Materials and Methods: The health impact due to ingestion of radionuclides from these foods was evaluated by the determination of activity concentration of radionuclides 238U, 232Th, 40K, and 137Cs using gamma spectrometry system with high-purity germanium detector and radiological hazards index in 16 samples collected in some markets, mall, and shops of Bamako-Mali. Results and Discussion: The average activity concentrations were 9.8±0.6 Bq/kg for 238U, 8.7±0.5 Bq/kg for 232Th, 162.9±7.9 Bq/kg for 40K, and 0.0035±0.0005 Bq/kg for 137Cs. The mean values of radiological hazard parameters such as annual committed effective dose, internal hazard index, and risk assessment from this work were within the dose criteria limits given by international organizations (International Commission on Radiological Protection and United Nations Scientific Committee on the Effects of Atomic Radiation) and national standards. Conclusion: The results show low public exposure to radioactivity and associated radiological impact on public health. Nevertheless, this study stipulates vital data for future research and regulatory authorities in Mali.

The Protective Effect of Selenium on Radiation in Rat (흰쥐에 있어 방사선에 대한 셀레늄의 보호효과)

  • Son, Eun-Joo;Ryu, Eun-soon
    • Journal of the Korean Society of Radiology
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    • v.13 no.3
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    • pp.439-444
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    • 2019
  • In this study, the radiation protection effects of selenium, known as a powerful antioxidant, were studied. After 14 days of oral injection of selenium into the rat, a full body irradiation of 10 Gy was carried out. And after 1 day, 3.5 day, 7 day and 21 day, we observed blood cell components and superoxide dismutase(SOD) and small intestine changes. Compared to irradiation groups, there was a significant protection effect of reducing the hematopoietic immune system damage in the irradiated group after selenium administration(p<0.05). Then, selenium is a valid ingredient that increases the activity of the superoxide Dismutase(SOD), and it is confirmed that it has an effect of inhibiting apoptosis expression of small intestinal cells by irradiation. Based on these results, selenium is considered to be an essential ingredient for protecting living things from radiation.

A Reference Container Concept for Spent Fuel Disposal : Structural safety for dimensioning of the reference container

  • Choi, Jong-Won;Kwon, Sang-Ki;Kang, Chul-Hyung;Kwon, Young-Joo
    • Journal of Radiation Protection and Research
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    • v.29 no.1
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    • pp.49-55
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    • 2004
  • This paper presents the mechanical and thermal stress analysis of a disposal canister to provide basic information for dimensioning the canister and configuration of the canister components. The structural stress analysis is carried out using a finite element analysis code, NISA, and focused on the structural strength of the canister against the expected external pressures due to the swelling of the bentonite buffer and the hydrostatic head, and the thermal load build up in the container.

Uncertainty and Sensitivity Analysis on A Biosphere Model

  • Park, Wan-Sou;Kim, Tae-Woon;Lee, Kun-Jai
    • Journal of Radiation Protection and Research
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    • v.15 no.2
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    • pp.101-112
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    • 1990
  • For the performance assessment of the radioactive waste disposal system (repository), a biosphere model is suggested. This biosphere model is intended to calculate the annual doses to man caused by the contaminated river water for eight pathways and four radionuclides. This model can also be applied to assess the radiological effects of contaminated well water. To account for the uncertainties on the model parameter values, parameter distributions are assigned to these model parameters. Then, Monte Carlo simulation method with Latin Hypercube sampling technique is used. Also, sensitivity analysis is performed by using the Spearman rank correlation coefficients. It is found that these methods are a very useful tool to treat uncertainties and sensitivities on the model parameter values and to analyze the biosphere model. A conversion factor is proposed to calculate the annual dose rate to humans arising from a unit radionuclide concentration in river water. This conversion factor allows for the substitution of the biosphere model in a probabilistic performance assessment computer code by one single variable.

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Nuclear Energy Depositions in the Primary End Shields and Side Primary Shield Systems (월성 2호기 종단 및 측면 차폐체에의 핵에너지축적 해석)

  • Kim, Kyo-Youn;Kim, Jong-Kyung
    • Journal of Radiation Protection and Research
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    • v.17 no.2
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    • pp.37-48
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    • 1992
  • It was carried out to analyze the nuclear energy deposition rates for the bulk shield components including materials of the primary end shield and side primary systems of Wolsong 2 during steady state operations at 100% full power using ANISN code. This paper has been prepared to support system design of Wolsong 2.

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Development of Prototype Liquid Scintillator System for Monitoring Liquid Radioactive Waste (배수 모니터링 액체섬광검출시스템의 프로토 타입 개발)

  • Nam, Uk-Won;Seon, Kwang-Il;Kong, Kyoung-Nam;Kim, Chang-Kyu;Lee, Dong-Myung;Lee, Sang-Kook
    • Journal of Radiation Protection and Research
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    • v.28 no.3
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    • pp.173-182
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    • 2003
  • A prototype liquid scillatillator system for measurement of multiple beta-labeled mixtures was developed and its characteristic was investigated. The signal processing system consists of two photomultiplier tubes and the coincident count circuit. The characteristic of the system was analyzed using 4 beta-labeled samples $(^3H,\;^{14}C,\;^{36}Cl\;and\;^{90}Sr)$. Beta spectra from the samples were obtained without radiation shielding, and the detection limits for each nuclides were estimated based on the spectra. The estimated detection limits were compared to the legal regulation values. It is found that the liquid radioactive nuclides are detectable well below the legal regulation values.

An Improvement of Estimation Method of Source Term to the Environment for Interfacing System LOCA for Typical PWR Using MELCOR code

  • Han, Seok-Jung;Kim, Tae-Woon;Ahn, Kwang-Il
    • Journal of Radiation Protection and Research
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    • v.42 no.2
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    • pp.106-113
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    • 2017
  • Background: Interfacing-system loss-of-coolant-accident (ISLOCA) has been identified as the most hazardous accident scenario in the typical PWR plants. The present study as an effort to improve the knowledge of the source term to the environment during ISLOCA focuses on an improvement of the estimation method. Materials and Methods: The improvement was performed to take into account an effect of broken pipeline and auxiliary building structures relevant to ISLOCA. An estimation of the source term to the environment was for the OPR-1000 plants by MELOCR code version 1.8.6. Results and Discussion: The key features of the source term showed that the massive amount of fission products departed from the beginning of core degradation to the vessel breach. Conclusion: The release amount of fission products may be affected by the broken pipeline and the auxiliary building structure associated with release pathway.

DEVELOPMENT OF POSITION-SENSITIVE PROTON RECOIL TELESCOPE (PSPRT)

  • Miura, Takako;Baba, Mamoru;Kawata, Naoki;Sanami, Toshiya
    • Journal of Radiation Protection and Research
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    • v.26 no.3
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    • pp.161-165
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    • 2001
  • We have developed a position-sensitive proton recoil telescope (PSPRT) which employs a position-sensitive photomultiplier (PS-PMT) and a scintillator for both a radiator and a proton-detector. This system is expected to achieve high energy resolution under a large solid angle, because it enables to obtain the information not only on the proton energy but also the recoil angle from the position data for both detectors. The response of the PSPRT for 14.1 MeV mono-energetic neutrons was measured, and the PSPRT proved to be operating as expected.

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