• Journal of Radiation Protection and Research
• /
• 제21권4호
• /
• pp.255-262
• /
• 1996

이 논문은 최근 한국원자력연구소(KAERI)와 미국 패시픽노스웨스트 국립연구소(일명, 바텔연구소, PNNL)이 개인선량계의 성능검사를 위한 미국 ANSI N13.11 기준에 근거하여 KAERI 방사선 측정/교정실험실에서 수행한 KAERI 기준 광자 및 베타 방사선장의 국제 상호비교 측정결과를 설명하고 있다. 두 기관이 각각 자국의 일차 표준에 소급성을 갖는 방사선 검출기와 방사선 측정장치를 사용하여 자유공기중에서 광자의 조사선량(율), 공기커마(율)와 베타선의 절대 흡수선량(율)을 측정한 결과, 광자선장에 대해서는 ${\pm}2.0%$을 베타선장에 대해서는${\pm}1.0%$의 오차범위 내에서 잘 일치하였다. 따라서 KAERI의 기준 광자 및 베타 방사선장은 국제표준에 잘 만족되고 있음이 입증되었으며 장차 방사선 도시메트리 연구개발의 국가 기술기반으로 활용될 수 있음이 확인되었다

• Journal of Radiation Protection and Research
• /
• 제26권3호
• /
• pp.243-248
• /
• 2001

Neutron reference fields of Korea Atomic Energy Research Institute (KAERI) for calibrating neutron measuring devices to be used in radiation workplace monitoring consist of two kinds of neutron spectra, the direct and the scattered neutron fields, which are produced by using radionuclide neutron sources, 252Cf and 241AmBe sources. Necessary parameters for calibration such as the anisotropy factor of each neutron source and the room-scattered fraction of some neutron surveymeters in the KAERI calibration facility were determined by calculation or measurement. Spectral measurement of scattered neutron fields were performed at each reference calibration point using a Bonner Multi-sphere Spectrometer (BMS) and the dosimetric quantities for calibration also estimated from the neutron energy spectra which were unfolded using the BUNKI code.

• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 1996년도 춘계학술발표회논문집(4)
• /
• pp.34-39
• /
• 1996

A series of measurements was peformed between KAERI and PNNL, U.S.A at KAERI secondary calibration laboratory to intercompare and verify the KAERI reference photon radiation fields by using air equivalent plastic walled ionization chambers, Different ionization chambers of two laboratories were used to determine the air kerma rate, free-in-air, at reference positions in the KAERI photon radiation fields, As the results, the agreement in the cross measurements between two laboratories was found to be within less than ${\pm}$ 3 %. This degree of consistency was considered to be encouraging, because each laboratory maintains independently its calibration traceablity with its national primary standard

• Journal of Radiation Protection and Research
• /
• 제44권2호
• /
• pp.72-78
• /
• 2019

Background: In the calibration and testing laboratory of Korea Atomic Energy Research Institute, the old X-ray generator used for the production of reference X-ray fields was replaced with a new one. For this newly installed X-ray irradiation system, beam alignment as well as the verification of beam qualities was conducted. Materials and Methods: The existing X-ray generator, Phillips MG325, was replaced with YXLON Y.TU 320-D03 in order to generate reference X-ray fields. Theoretical calculations and Monte Carlo simulations were used to determine initial filter thickness. Beam alignment was performed in three steps to deliver a homogeneous radiation dosage to the target at different distances. Finally, the half-value layers were measured for different X-ray fields to verify beam qualities by using an ion chamber. Results and Discussion: Beam alignment was performed in three steps, and collimators and other components were arranged to maintain the uniformity of the mean air kerma rate within ${\pm}2.5%$ at the effective beam diameter of 28 cm. The beam quality was verified by using half-value layer measurement methods specified by American National Standard Institute (ANSI) N13.11-2009 and International Organization for Standardization (ISO)-4037. For each of the nine beams than can be generated by the new X-ray irradiation system, air kerma rates for X-ray fields of different beam qualifies were measured. The results showed that each air kerma rate and homogeneity coefficient of the first and second half-value layers were within ${\pm}5%$ of the recommended values in the standard documents. Conclusion: The results showed that the new X-ray irradiation system provides beam qualities that are as high as moderate beam qualities offered by National Institute of Standards and Technology in ANSI N13.11-2009 and those for narrow-spectrum series of ISO-4037.

• Journal of Radiation Protection and Research
• /
• 제23권4호
• /
• pp.229-236
• /
• 1998

개인 피폭선량 평가의 검증체계를 확립함에 있어서 기본적으로 갖추어야할 방사선장은 감마선, X-선, 베타선 및 중성자이다 금년에 한국원자력안전기술원에서는 중성자를 제외한 방사선장을 위한 기준조사장치(빔)를 확보하였다. 이 기준조사빔이 국제적으로 소급할 수 있는 방사선장의 역할을 수행할 수 있도록 하기 위하여 국제 표준기구규정 및 선진국의 표준규격 등의 기준과 요구조건에 충족되도록 하였다. 본 논문은 감마선장에 대한 기준조사장치에 관한 것으로서의 기여도 및 방사선장의 균질도를 평가하였고, 이를 국제 기준과 비교한 결과 국내 및 국제 기준을 잘 만족하고 있는 것으로 평가되었다. 또한, 측정된 공기커마율은 $^{137}Cs$ 선원에 대하여 $0.1891{\sim}23.4967{\mu}Gy/s$, $^{60}Co$ 선원에 대해서는 $0.588{\sim}15.9954{\mu}$Gy/s의 값으로 결정하였으며, 공기커마율이 가지는 불확도는 95% 신뢰도 범위에서 2.5% 이내로 결정되었다. 측정된 공기커마율의 신뢰성을 검증하기 위하여 전리함의 교정정수를 독일 PTB의 교정정수에 대하여 재평가한 결과 교정정수가 가지는 불착도(1.2%) 범위 내에서 일치하고 있었으며, 미국의 측정값과 비교한 결과 0.03% 범위 내에서 일치하고 있음이 판명되었다. 그러므로 한국원자력안전기술원에 설치된 감마선장은 국내의 표준 소급체계를 유지하고 있을 뿐만 아니라 미국 및 독일의 소급체계를 확보하게 되었고, 국내 및 국제 기준 방사선장으로 활용 가능하게 되었다.

• Journal of Radiation Protection and Research
• /
• 제41권3호
• /
• pp.211-215
• /
• 2016

Background: The moderated neutron calibration fields using $^{241}Am$-Be sources and a graphite moderator have been constructed at the Facility of Radiation Standard (FRS) in the Japan Atomic Energy Agency (JAEA). Materials and Methods: The neutron spectra of the fields were evaluated by the Monte-Carlo calculations and measurements using the Bonner Multi-sphere Spectrometer. Results and Discussion: The fields have continuous neutron spectra from several MeV to thermal neutron energy, with fluence-averaged energies of 0.84 MeV and 0.60 MeV. Reference values of fluence rates and ambient/personal dose equivalent rates were determined from neutron spectra by measurements. Conclusion: Currently, the fields are available for calibration or performance test of neutron measuring instruments.

• Journal of Radiation Protection and Research
• /
• 제28권4호
• /
• pp.327-335
• /
• 2003

The commercially available neutron survey meter, the REM500, which uses a tissue equivalent proportional counter (TEPC) and the self-constructed TEPC were used to determine the microdosimetric quantities of several neutron calibration fields at Korea Atomic Energy Research Institute (KAERI). Microdosimetric spectra, absorbed dose, dose equivalent as well as quality factor were derived and compared with several neutron fields which were produced by using the shadow objects to make neutron scattered and being used as a kind of realistic neutron calibration fields at KAERI. The response of REM500 as a function of mean energy was evaluated with these neutron fields using the counts measured and the predetermined reference value. The response of the self-made TEPC and the REM500 was compared using one of the neutron calibration filelds of a $^{252}Cf$ source. The reference quantities of scattered neutron calibration fields were determined using a Bonner Sphere (BS). The value of frequency-mean lineal energy, dose-mean lineal energy and quality factor of two $^{252}Cf$ sources (unmoderated and $D_2O$ moderated) were determined to check the differences in the reference neutron fields between KAERI and Pacific Northwest National Laboratory (PNNL, USA) and the results were in good agreement within 1%. It means that there is no big difference in dosimetric quantifies of neutron calibration fields of two laboratories.

• 대한방사선기술학회지:방사선기술과학
• /
• 제41권3호
• /
• pp.201-207
• /
• 2018

The purpose of this study is to evaluate the performance of a "stealth chamber" as a novel reference chamber for measuring percentage depth dose (PDD) and profile of 6, 8 and 10 MV photon energies. The PDD curves and dose profiles with fields ranging from $3{\times}3$ to $25{\times}25cm^2$ were acquired from measurements by using the stealth chamber and CC 13 chamber as reference chamber. All measurements were performed with Varian VitalBeam linear accelerator. In order to assess the performance of stealth chamber, PDD curves and profiles measured with stealth chamber were compared with measurement data using CC13 chamber. For PPDs measured with both chambers, the dosimetric parameters such as $d_{max}$ (depth of maximum dose), $D_{50}$ (PDD at 50 mm depth), and $D_{100}$ (PDD at 100 mm depth) were analyzed. Moreover, root mean square error (RMSE) values for profiles at $d_{max}$ and 100 mm depth were evaluated. The measured PDDs and profiles between the stealth chamber and CC13 chamber as reference detector had almost comparable. For PDDs, the evaluated dosimetric parameters were observed small difference (<1%) for all energies and field sizes, except for $d_{max}$ less than 2 mm. In addition, the difference of RMSEs for profiles at $d_{max}$ and 100 mm depth was similar for both chambers. This study confirmed that the use of stealth chamber for measuring commission beam data is a feasible as reference chamber for fields ranging from $3{\times}3$ to $20{\times}20cm^2$. Furthermore, it has an advantage with respect to measurement of the small fields (less than $3{\times}3cm^2$ field) although not performed in this study.

• 한국의학물리학회지:의학물리
• /
• 제30권2호
• /
• pp.59-63
• /
• 2019

Purpose: To manage radiation measurement equipment, a web-based management program has been developed in this study. Materials and Methods: This program is based on a web service and Java Server Pages (JSP) and employs compatibility and accessibility. Results: The first step in the workflow has been designed to create accounts for each user or organization and to log in. The program consists of two parts: fields for listed instruments, and measurement information. The instruments for measuring radiation listed in this program are as follows: ionization chambers, survey meters, thermometers, barometers, electrometers, and phantoms. Instrument properties can be put in the recording fields and browsing for associated instruments can be performed. The main part of the program is the cross-calibration for each ion chamber. For instance, the ionization chamber to be used as a relative dosimeter can be registered by cross-calibration data with a reference chamber calibrated by an accredited laboratory. This program supports methods using the central axis transfer theory for cross-calibration for the ionization chambers. The reference and field ionization chambers were placed in a solid water phantom along the beam central axis at two different depths, and then the positions were switched. Each measured value was used for calculating the cross-calibration factor. Conclusions: Because many instruments are used and managed in radiation oncology departments, systematic, traceable recording is very important. The web-based program developed in this study is expected to be used effectively in the maintenance of radiation measurement instruments.

• Nuclear Engineering and Technology
• /
• 제55권6호
• /
• pp.1949-1958
• /
• 2023

The International Commission on Radiological Protection (ICRP) Publication 116 was released to provide a comprehensive dataset of the dose coefficients (DCs) for external exposures produced with the adult reference voxel phantoms of ICRP Publication 110. Although an advanced skeletal dosimetry method for photons and neutrons using fluence-to-dose response functions (DRFs) was introduced in ICRP Publication 116, the ICRP-116 skeletal DCs were calculated by using the simple method conventionally used (i.e., doses to red bone marrow and endosteum approximated by doses to spongiosa and/or medullary cavities). In the present study, the photon and neutron DRFs were used to produce skeletal DCs of the ICRP-110 reference phantoms, which were then compared with the ICRP-116 DCs. For photons, there were significant differences by up to ~2.8 times especially at energies <0.3 MeV. For neutrons, the differences were generally small over the entire energy region (mostly <20%). The general impact of the DRF-based skeletal DCs on the effective dose calculations was negligibly small, supporting the validity of the ICRP-116 effective DCs despite their skeletal DCs derived from the simple method. Meanwhile, we believe that the DRF-based skeletal DCs could be beneficial in better estimates of skeletal doses of individuals for risk assessments.