• Title/Summary/Keyword: Radiation Generator

Search Result 237, Processing Time 0.025 seconds

A Study On Low Radiation Measurement of Radiation Measuring Devices and Improvement of Reaction Speed according to the Rapid Change of Radiation Dose (방사선 측정장치의 저준위 방사선 측정과 방사선량의 급격한 변화에 따른 장치의 반응 속도개선에 관한 연구)

  • Lee, Joo-Hyun;Lee, Seung-Ho
    • Journal of IKEEE
    • /
    • v.18 no.4
    • /
    • pp.544-551
    • /
    • 2014
  • This paper suggests an algorithm to measure low-level radiation by radiation measuring devices, and the other algorithm to improve reaction speed of the device to better respond to dramatic changes in radiation amount. The former algorithm to improve the accuracy of measuring low-level radiation takes advantage of a dual window radiation measurement method which is based on accumulated average of pulses gathered by a radiation measuring sensor. The latter algorithm is to enhance reaction speed of a measuring device to more sensitively react to dramatic changes in radiation amount by adopting a dual window radiation measurement method which analyzes data patterns newly put into for six seconds. To verify the suggested algorithms, a hardware-which consists of sensor and high-voltage generator, controller, charger and power supply circuit, wireless communication part, and display part-was used. Tests conducted on the dual window radiation measurement method as used in the suggested algorithm have proved that accuracy improves to measure low-level radiation of 5uSv/h, and linearity also gets better. Other tests were conducted to see whether the suggested algorithm enhances the reaction speed of a radiation measuring device so that the device responds better to dramatically changing radiation amount. The experimental results have shown meaningful changes in numbers after six seconds. Therefore, the conclusions are made that the algorithm enhances the reaction speed of the device.

Development of DAP(Dose Area Product) for Radiation Evaluation of Medical and Industrial X-ray generator (의료 및 산업용 X-선 발생장치의 선량평가를 위한 면적선량계(DAP) 개발)

  • Kwak, Dong-Hoon;Lee, Sang-Heon;Lee, Seung-Ho
    • Journal of IKEEE
    • /
    • v.22 no.2
    • /
    • pp.495-498
    • /
    • 2018
  • In this paper, we propose an DAP system for dose evaluation of medical and industrial X-ray generator. Based on the DAP measurement technique using the Ion-Chamber, the proposed system can clearly measure the exposure radiation dose generated by the diagnostic X-ray apparatus. The hardware part of the DAP measures the amount of charge in the air that is captured by an X-ray. The high-speed processing algorithm part for cumulative radiation dose measurement through microcurrent measures the amount of charge captured by X-ray at a low implementation cost (power) with no input loss. The wired/wireless transmission/reception protocol part synchronized with the operation of the X-ray generator improves communication speed. The PC-based control program part for interlocking and aging measures the amount of X-ray generated in real time and enables measurement graphs and numerical value monitoring through PC GUI. As a result of evaluating the performance of the proposed system in an accredited testing laboratory, the measured values using DAP increased linearly in each energy band (30, 60, 100, 150 kV). In addition, since the standard deviation of the measured value at the point of 4 division was ${\pm}1.25%$, it was confirmed that the DAP showed uniform measurements regardless of location. It was confirmed that the normal operation was not less than ${\pm}4.2%$ of the international standard.

A Base Study on the Constancy Quality Control Test and Clause of Diagnosis Radiation Equipment (진단용 방사선 발생장치의 수시 정도관리 항목 및 기준에 관한 기초 연구)

  • Heo, Yeji;Kim, Kyotae;Noh, Sicheul;Nam, Sanghee;Park, Jikoon
    • Journal of the Korean Society of Radiology
    • /
    • v.8 no.3
    • /
    • pp.105-110
    • /
    • 2014
  • Diagnostic radiation equipment diagnosis and treatment of disease of recent plays a central role, but this is based on the assumption of an appropriate balance of benefits and risks of diagnostic. If balance is not maintained has the potential to give an adverse effect on the health of the public. In the case of an overseas, the importance of (QA) quality assurance of medical equipment is growing, but evaluation criteria of quality assurance has not been clearly presented in domestic. Therefore, the modernization of medical equipment from the point at which the degree of cycle-by-cycle management system of foreign national to be suitable for diagnostic radiation generator entry and quality control standards by introducing a tailoring is necessary. In this study the most frequently used diagnostic radiation generator X-ray imaging apparatus of the general three-year periodic inspections at any time between the periodic inspection items and quality control methods and standards for the establishment of the United States, Canada and abroad, and international electronic literature search Technical Committee (International Electro-technical Commission, IEC) were compared with the provisions of item. Based on the national quality control items when opening frequent inspection items and standards presented as a basis for setting up study.

Monte Carlo Study of MOSFET Dosimeter Dose Correction Factors Considering Energy Spectrum of Radiation Field in a Steam Generator Channel Head (원전 증기발생기 수실 내 에너지 스펙트럼을 고려한 MOSFET 방사선검출기 선량보정인자 결정에 관한 몬테칼로 전산모사 연구)

  • Cho, Sung-Koo;Choi, Sang-Hyoun;Kim, Chan-Hyeong
    • Journal of Radiation Protection and Research
    • /
    • v.31 no.4
    • /
    • pp.165-171
    • /
    • 2006
  • In Korea, a real-time effective dose measurement system is in development. The system uses 32 high-sensitivity MOSFET dosimeters to measure radiation doses at various organ locations in an anthropomorphic physical phantom. The MOSFET dosimeters are, however, mainly made of silicon and shows some degree of energy and angular dependence especially for low energy photons. This study determines the correction factors to correct for these dependences of the MOSFET dosimeters for accurate measurement of radiation doses at organ locations in the phantom. For this, first, the dose correction factors of MOSFET dosimeters were determined for the energy spectrum in the steam generator channel of the Kori Nuclear Power Plant Unit #1 by Monte Carlo simulations. Then, the results were compared with the dose correction factors from 0.652 MeV and 1.25 MeV mono-energetic photons. The difference of the dose correction factors were found very negligible $(\leq1.5%)$, which in general shows that the dose corrections factors determined from 0.662 MeV and 1.25 MeV can be in a steam general channel head of a nuclear power plant. The measured effective dose was generally found to decrease bit $\sim7%$ when we apply the dose correction factors.

Study on the Radiation Pattern of Radiated Emission above 1 GHz (1 GHz 이상에서의 복사 방출 방사 패턴에 관한 연구)

  • Chung, Yeon-Choon;Lee, Soon-Yong;Kwun, Suk-Tai
    • The Journal of Korean Institute of Electromagnetic Engineering and Science
    • /
    • v.22 no.3
    • /
    • pp.336-344
    • /
    • 2011
  • The purpose of this study is to analyze the radiation-pattern characteristics above 1 GHz for the electromagnetic wave radiated from multi-slot such as ventilations, etc. on the enclosure of an EUT and so to make recommendations for suitable test methods. An experimental EUT was formed by putting a comb-generator at the center of a rectangular enclosure with 4 slots, and its radiation pattern was analyzed in the frequency range of 1~6 GHz. As analysis results, multi-lobe appears above 2 GHz and the number of multi-lobes is growing as the frequency increases. And real radiated-emission measurements were performed for the experimental EUT by scanning a receiving antenna in the height of 1~4 m and tilting toward maximum radiation, as well as setting the height of a receiving antenna to the central position of the EUT which is prescribed at the present standards. The measured results are +12.8 dB in the scanning and +16.4 in the scanning and tilting compared with the present standard test method. Therefore, the latter must be revised in order to consider the radiation pattern above 1 GHz.

An Optimization Study on the Radiation Management in Nuclear Power Plants (원자력 발전소 방사선 관리의 최적화에 관한 연구)

  • Song, Jong-Soon
    • Journal of Radiation Protection and Research
    • /
    • v.18 no.1
    • /
    • pp.71-82
    • /
    • 1993
  • It is a fundamental element of the nuclear power plant operation to assess exactly the occupational radiation exposure. And, according to recently published ICRP 60 recommendation, it is needed to reduce individual radiaton exposure limit further. In this paper, an optimization techique was suggested for selection of alternatives for reducing occupational radiation exposure, and used in reviewing alternatives given by a plant utility. After the basic analysis, sensitivity analysis was performed to consider the variabilities of the economic variables. From the result, it was found that an option using steam generator nozzle dam and torquing machine was the best with respect to total benefits, and in case of multi-attribute utility analysis, an option using Co-No seal had the highest utility. Therefore, it was necessary to apply more than one technique togeter in optimization study and to consider qualitative factor, too.

  • PDF

A Study on Regulations Through Analysis of the Status of Radiation Workers and Related Workers and Satisfaction Survey in the Radiology Department (방사선작업종사자 및 방사선관계종사자의 현황 분석과 교내 실습 만족도 조사를 통한 방사선(학)과의 규제에 대한 고찰)

  • Jung, Hyunseo;Lee, Yong-Ki;Ahn, Sung-Min
    • Journal of the Korean Society of Radiology
    • /
    • v.16 no.3
    • /
    • pp.327-334
    • /
    • 2022
  • In this study, the purpose of this study was to conduct a basic study on the effectiveness and feasibility of the regulation of the Nuclear Safety Act for the department of radiology by examining the questionnaire on the satisfaction of on-campus practice while attending the department of radiology and the current status of radiation workers and radiation related workers. As for the satisfaction of the workers who were designated as frequent visitors while attending the department of radiology and did not handle and operate the radiation generator during on-campus training, 34.62% of the workers answered 'not satisfied'. On the other hand, 50% of workers who were designated as radiation workers while attending school or who were enrolled in school before the regulation of the nuclear safety act and handled and operated radiation generators were 'satisfied' at 50%. In addition, the annual exposure dose of radiation workers in educational institutions was found to be less than 0.05 mSv. If you look at the trends of radiation workers and radiation workers, it can be seen that students who graduate from the Department of Radiology find the most employment in the field dealing with diagnostic radiation generators registered as radiation workers among medical institutions. Therefore, by easing the regulations of the current Nuclear Safety Act or by amending the medical act and the rules on the safety management of diagnostic radiation generating devices, etc. It is presumed that something is necessary.

CR장치와 일반 촬영 장치에서 피폭선량 측정과 촬영조건표 작성에 관한 연구

  • Kim, Heung-Tae;Gwon, Su-Il;Gwon, Dal-Gwan;Kim, Hwa-Gon
    • Korean Journal of Digital Imaging in Medicine
    • /
    • v.3 no.1
    • /
    • pp.76-84
    • /
    • 1997
  • We tried to find any factor to reduce the exposure dose with ST-VA type generator which has the higher exposure dose. The guideline recommended by the provisions of IAEA regulation is being used at the time of radiation exposure and almost of those equipments used for this study had less amount of doses than those in the guideline. The FCR may be possible to decrease a certain amount of dose with effective applications of it's automatic image compensation utilities and the verifying function in PACS. Next time, it is required to add a great number of hospitals for wide range of studios and measurements, and make standard exposure Control table which will bing in practice, material decrease of dose volumes when radiation exposure.

  • PDF

Experiments for the Characteristic Evaluation of Pollutant Transport in Tidal Influenced Region (조파역내 오염물 이동특성 평가 실험)

  • Park, Geon Hyeong;Kim, Ki Chul;Jung, Sung Hee;Suh, Kyung Suk
    • Journal of Radiation Industry
    • /
    • v.4 no.4
    • /
    • pp.391-395
    • /
    • 2010
  • The characteristics for pollutant transport in tidal influenced area was investigated using tidal wave hydraulic scale model. Hydraulic scale model was composed of the tidal generator, attenuation area and channel. Also, wave height, current meter and conductivity meter were used with the measured instruments in hydraulic scale model. NaCl with a tracer was used to evaluate the advection phenomena under the different velocity profiles. The arrival time of the maximum concentration in the condition of the relatively fast velocity was measured about 30 seconds faster than ones in the conditions of low velocity. The measured concentrations of the tracer were shown in the detection points of the flow direction consecutively.

Investigation of Response of Several Neutron Surveymeters by a DT Neutron Generator (DT 중성자 발생기에 의한 중성자 검출기 반응도 조사)

  • Kim, Sang-In;Jang, In-Su;Kim, Jang-Lyul;Lee, Jung-Il;Kim, Bong-Hwan
    • Journal of Radiation Protection and Research
    • /
    • v.37 no.1
    • /
    • pp.35-40
    • /
    • 2012
  • Several neutron measuring devices were tested under the neutron fields characterized with two distinct kinds of thermal and fast neutron spectrum. These neutron fields were constructed by the mixing of both thermal neutron fields and fast neutron fields. The thermal neutron field was constructed using by a graphite pile with eight AmBe neutron sources. The fast neutron field of 14 MeV was made by a DT neutron generator. In order to change the fraction of fast neutron fluence rate in each neutron fields, a neutron generator was placed in the thermal neutron field at 50 cm and 150 cm from the reference position. The polyethylene neutron collimator was used to make moderated 14 MeV neutron field. These neutron spectra were measured by using a Bonner sphere system with an LiI scintillator, and dosimetric quantities delivered to neutron surveymeters were determined from these measurement results.