• Title/Summary/Keyword: System of radiation protection

Search Result 402, Processing Time 0.025 seconds

INFORMATION SYSTEM ON INTEGRATED RADIATION SAFETY (ISIRS) AND ORPHAN SOURCES CONTROL IN KOREA

  • Lee, Dewhey
    • Journal of Radiation Protection and Research
    • /
    • v.26 no.3
    • /
    • pp.255-263
    • /
    • 2001
  • An Orphan Sources Control program controlled by a web based information system in Korea has been developed to satisfy the national demand on a total management of and integrated radiation safety. There are, currently, three approaches going on to control and manage the orphan sources in Korea. First, Korean regulatory authority has been conducting scrutinizing investigation on and thoroughly monitoring the possession of unlicensed radioactive sources from the late 1990s. Second, the regulatory authority will fully operate an information system on radiation safety to effectively trace and monitor all radioactive sources in the country by the mid 2001. Finally, the regulatory authority strongly advises steel mill companies to closely scrutinize and inspect the scrap metals when they attempt to reutilize metals to prevent from being contaminated by uncontrolled sources through the scrap monitoring systems.

  • PDF

Developement of Radiation Measuring System using Wireless Communication (무선통신을 이용한 방사선측정 시스템 개발)

  • Lee, Bong-Jae;Chang, Si-Young
    • Journal of Radiation Protection and Research
    • /
    • v.20 no.2
    • /
    • pp.85-95
    • /
    • 1995
  • Radiation measuring system using wireless communication method with single channel has been diveloped and tested. In this system, radiation signals from GM tube are transformed into digital pulses in pulse processing circuit and modulated in FSK (frequency shift keying) circuit for digital communication and then wirelessly transmitted to a receiving unit. The digital pulses received are then demodulated in FSK circuit and converted into radiation dose/dose rate in the data acquisition unit to display on the screen of a personal computer. The performance of this system was evaluated by using both a pulse generator and a standard radiation source(Cs-137). In both cases, digital pulses with 5V were observed in pulse processing circuit without distortion of their shape through wireless communication system. The experimental results of radiation measurement by this system after several test-irradiation of GM detector to a standard radiation source(Cs-137), showed good agreement with irradiation dose rate within 10% difference, and proved that this system could be effectively utillized as radiation measuring instrument. It is expected that this wireless radiation measuring system developed for the first time in Korea, can be used as a radiation monitor as well as a personal dosimeter if we can further improve this system to adopt wireless multichannel communication system.

  • PDF

Study of a Protection Technology to the Transient Radiation for the Semiconductors (반도체에 대한 과도방사선 방호기술연구)

  • Lee, Nam-ho;oh, Sung-Chan;Jeong, Sang-hun;Hwang, Young-gwan;Kim, Jong-yul
    • Proceedings of the Korean Institute of Information and Commucation Sciences Conference
    • /
    • 2013.05a
    • /
    • pp.1023-1026
    • /
    • 2013
  • The electronic equipment which was exposed to high level pulsed radiation is damaged as Upset, Latchup, and Burnout. Those damages has come from the instantaneous photocurrent from electron-hole pairs generated in itself. Such damages appeared as losses of power in military weapon system or of blackout in aerospace equipment and eventually caused in gross loss of national. In this paper, we have implemented a RDC(Radiation detection and control module) as part of the radiation protection technology of the electronic equipment or devices from the pulsed gamma radiation. The RDC which is composed of pulsed gamma-ray detection sensor, signal processors, and pulse generator is designed to protect the important electronic circuits from the pulse radiation. To verify the functionality of the RDC, LM118s which had damaged by the pulse radiation were tested. The test results showed that the test sample applied with a RDC was worked well in spite of the irradiation of the same pulse radiation. Through the experiments we could confirm that the radiation protection technology implemented with RDC had the functionality of radiation protection to the electronic devices.

  • PDF

Medical Preparedness in Radiation Accidents (방사선 사고시의 의료대책)

  • Kim, Eun-Sil;Kim, Jong-Soon
    • Journal of Radiation Protection and Research
    • /
    • v.21 no.3
    • /
    • pp.201-215
    • /
    • 1996
  • Radiation and radioactive materials serve man in many beneficial ways. Diagnostic X-ray, radiation therapy, and other nuclear medicine uses of radioactivity save thousands of lives each year. Industrial application of radiation, such as radiography, make many manufactured products more reliable and less expensive. Nuclear power plants are producing more electrical power each year and reducing our dependence on imported oil. However, radiation can and dose produce harmful effects particularly as the reault of a radiation accident in which a victim receives as the result of a radiation accident in which a victim receives a large dose. Fortunately such accidents are very rare and recently we need more electric power produced by nuclear power plants. Considering increase of use of radiation or radioactive materials, we have to establish the radiological emergency response system prepared for radiation accidents.

  • PDF

AN ASSESSMENT OF THE RADIATION DOSE RATE DUE TO AN OCCURRENCE OF THE DEFECT ON THE SPENT NUCLEAR FUEL ROD

  • Lee, Sang-Hun;Moon, Joo-Hyun
    • Journal of Radiation Protection and Research
    • /
    • v.34 no.3
    • /
    • pp.144-150
    • /
    • 2009
  • This study examines how much the radiation dose rate around it varies if a crack occurs on the spent nuclear fuel rod. The spent nuclear fuel rod to be examined is that of Kori unit 3&4. The source terms are evaluated using the ORIGEN-ARP that is part of the version 5.1 of the SCALE package. The radiation dose rate is assessed using the TORT. To check if the structure of a fuel rod is appropriately modeled in the TORT calculation, the calculation results by the TORT are compared with those by the ANISN for the same case. From the code simulation, it is known that if a crack occurs on the spent nuclear fuel rod, the neutron dose rate varies depending on what material is the crack filled with, but the gamma dose rate varies irrespective of type of the material that the crack is filled with.

Development of an open-source GUI computer program for modelling irradiation of multi-segmented phantoms using grid-based system for PHITS

  • Hiroshi Watabe;Kwan Ngok Yu;Nursel Safakatti;Mehrdad Shahmohammadi Beni
    • Nuclear Engineering and Technology
    • /
    • v.55 no.1
    • /
    • pp.373-377
    • /
    • 2023
  • The Monte Carlo (MC) method has become an indispensable part of the nuclear radiation research field. Several widely used and well-known MC packages were developed for simulation of radiation transport and interaction with matter. All these MC packages require users to prepare an input script. The input script can become lengthy for complex models. The process of preparing these input scripts is time-consuming and error-prone. In the present work, we have developed an open-source GUI computer program for modelling radiation transport and interaction in multi-segmented slab phantoms using grid-based system for the widely used PHITS MC package. The developed tools would be useful for future users of PHITS MC package and particularly inexperienced users. The present program is distributed under GPL license and all users can freely download, modify and redistribute the program without any restrictions.

An Off-site Screening Process for the Public in Radiation Emergencies and Disasters

  • Yoon, Seokwon;HA, Wi-Ho;Jin, Young-Woo
    • Journal of Radiation Protection and Research
    • /
    • v.41 no.3
    • /
    • pp.301-309
    • /
    • 2016
  • Background: A contamination screening process for the local population in radiation emergencies is discussed. Materials and Methods: We present an overview of the relevant Korean governmental regulations that underpin the development of an effective response system. Moreover, case studies of foreign countries responding to mass casualties are presented, and indicate that responses should be able to handle a large demand for contamination screening of the local public as well as screening of the immediate victims of the incident. Results and Discussion: We propose operating procedures for an off-site contamination screening post operated by the local government for members of the public who have not been directly harmed in the accident. In order to devise screening categories, sorting strategies assessing contamination and exposure are discussed, as well as a psychological response system. Conclusion: This study will lead to the effective operation of contamination screening clinics if an accident occurs. Furthermore, the role of contamination screening clinics in the overall context of the radiation emergency treatment system should be clearly established.

On-line Gamma Monitoring System for Environmental Radiation Measurement around KAERI-site (KAERI 부지 주변의 환경선량 측정을 위한 온라인 감마선량 감시시스템)

  • Lee, Chang-Woo;Park, Doo-Won;Lee, Won-Yun;Choi, Yong-Ho;Hong, Kwang-Hee;Kim, Sam-Rang;Lee, Hyun-Duk;Lee, Jeong-Ho
    • Journal of Radiation Protection and Research
    • /
    • v.19 no.2
    • /
    • pp.147-156
    • /
    • 1994
  • On-line gamma monitoring system around KAERI-site was set up to monitor the radiation fluctuations in environment. Data on gamma exposure rates measured by the ionication chamber in the monitoring posts are transmitted to a computer of central control station with. radio telemetry transmission modem and monitored in real time. Radio telemetry transmission system is economical and reliable on handling and storing of data. This monitroing system can triger an early warning system in the event of abnormal radiation levels.

  • PDF

A LIMITED SURVEY OF DENTAL X-RAY UNITS AND PROTECTION IN KOREA (치과 X선발생장치 및 방어에 관한 조사연구)

  • Park T.W.
    • Journal of Korean Academy of Oral and Maxillofacial Radiology
    • /
    • v.10 no.1
    • /
    • pp.57-61
    • /
    • 1980
  • In dental roentgenograph it is of mutual benefit to the patient and the dentist to use the minimum amount of radiation capable of producing roentgenograms with maximum interprtive informations. Recent increases in the number of diagnostic x-ray examinations made in this country have caused attention to be paid to the quantity of radiation delivered to the population and operator. The purposes of this study was to assess the quality of dental x-ray units, the amount of films, the average processing procedures and the radiation protection methods in korea. The results were as following: 1. Most of radiation generating system were used in low voltage such as 60Kvp, 10㎃. 2. High sensitivity films such as 'D' group of Kodak or Rinn were mainly used and average 14.7 films used per weeks. 3. Some dentists practiced visual processing technic in simple dark room, and others used instant films. 4. 68.26% of patient held the film themselves, but 27.30% were assisted by dentists film holding. 5. In radiation protection method, 7.85% of dentists had protection equipments such as protective barrier, 2.73% wore protective apron, 27.9% made it a rules to avoid beam, and 7.51% used to maintain a distance from the radiation source.

  • PDF

General Requirements Pertaining to Radiation Protection in Diagnostic X-ray Equipment -KFDA DRS 1-1-3 : 2008 base on IEC 60601-1-3:2008- (진단용 엑스선 장치에 있어서 방사선 방어에 대한 일반 요구사항 -IEC 60601-1-3:2008에 근거한 KFDA DRS 1-1-3:2008-)

  • Kang, Hee-Doo;Dong, Kyung-Rae;Kweon, Dae-Cheol;Choi, Jun-Gu;Jeong, Jae-Ho;Jung, Jae-Eun;Ryu, Young-Hwan
    • Korean Journal of Digital Imaging in Medicine
    • /
    • v.11 no.2
    • /
    • pp.69-77
    • /
    • 2009
  • This study gives an account of the collateral standards in IEC 60601-1-3: 2008 specifying the general requirements for basic safety and essential performance of diagnostic X-ray equipment regarding radiation protection as it pertains to the production of X-rays. The collateral standards establish general requirements for safety regarding ionization radiation in diagnostic radiation systems and describe a verifiable evaluation method of suitable requirements regarding control over the lowest possible dose equivalent for patients, radiologic technologists, and others. The particular standards for each equipment can be determined by the general requirements in the collateral standard and the particular standard is followed in the risk management file. The guidelines for radiation safety of diagnostic radiation systems is written up in ISO 13485, ISO 14971, IEC 60601-1-3(2002)1st edition, medical electric equipment part 1-3, and the general requirements for safety-collateral standards: programmable electrical medical systems. Therefore the diagnostic radiation system protects citizens' health rights with the establishment and revisions of laws and standards for diagnostic radiation systems as a background for the general requirements of radiation safe guards applies, as an international trend, standards regarding the medical radiation safety management. The diagnostic radiation system will also assure competitive power through a conforming evaluation unifying the differing standards, technical specifications, and recognized processes.

  • PDF