개인방사선피폭선량평가

이형섭,김장렬,윤석철,이상윤 대한방사선 방어학회 1994 방사선방어학회지 Vol.19 No.2

최근, 개인방사선피폭선량평가에 관한 기술기준이 과학기술처에 의해 고시됨에 따라 국내에서도 개인선량계를 이용한 체외피폭선량평가결과의 신뢰성 문제가 크게 대두되고 있다. 한국원자력연구소에서는 이러한 구내의 상황을 인식하고 자체적인 신뢰성 확보를 위해 미국의 Oak Ridge국립연구소의 주관하에 개인피폭선량의 평가에 관한 국제상호비교검증시험(Personnel Dosimetry Intercomparison Study ; PDIS) 을 수행하였다. 비교 검증시험에는 한국원자력연구소에서 사용하고 있는 Teledyne PB-3 열형광선량계가 사용되였으며 선량게산 알고리즘은 Teledyne PB-3 version1.5-1989를 사용하였다. 본 연구에서는 지금까지 실시된 PDIS의 결과를 요약하고 현재 PB-3 시스템의 개인선량평가성능에 대해 고찰하였으며, 선량평가절차에 대한 문제점 도출을 통하여 직업적 방사선피폭선량 평가능력의 향상을 위한 방안을 제시하였다. Recently, the Ministry of Science and Technology issued a Ministerial Ordinance (N0 1992-15) about the technical criteria on personnel radiation dosimetry. In today's climate, it is important to demonstrate and document that the processor's systems and services to others meet national standards of quality. The purpose of this study is to verify the performance of the Teledyne PB-3 personnel dosimetry system that is generally used in Korea Atomic Energy Research Institute (KAERI) by intercomparison with Oak Ridge National Laboratory. The KAERI has been participated in this personnel dosimetry intercomparison study(PDIS) program since 1991 and it could be possible to test and calibrate personnel monitoring system. This report presents a summary and analysis of by about 50 does equivalent measurements reported for PDIS-16 through 18 (1991-1993) with emphasis on neutron does equivalent sensitivity, accuracy and methods to improve personnel dosimetry performance are also discussed.

LiF:Mg,Cu,Na,Si TL 소자의 선량계적 특성

남영미,김장렬,장시영 대한방사선 방어학회 2001 방사선방어학회지 Vol.26 No.1

최근 개발된 방사선량 측정용 LiF:Mg,Cu,Na,Si TL 소자의 글로우 곡선, 방출스펙트럼, 광자에 대한 선량의존성, 에너지의존성 및 페이딩 등과 같은 물리적 및 선량계적 특성들을 연구하였다. LiF:Mg,Cu,Na,Si TL 소자는 LiF:Mg,Cu,Na,Si TL 분말에 압력을 가한 후 소결하는 방법으로 제조되었다. 방사선에 대한 특성을 알아보기 위하여 광자선 조사는 한국원자력연구소의 X선 발생 장치 및 137Cs γ선 원격조사장치를 이용하였으며, 사용된 광자선 에너지 범위는 20-662keV, 선량 범위는 10-6-102 Gy이었다. 글로우 곡선은 수동형의 TLD 판독장치 (System 310, Teledyne)로 질소를 흘리면서 선형적인 가열률로 측정하였으며, TL 강도는 글로우 곡선을 전체 적분한 면적으로 평가하였다. 5℃·s-1의 선형적인 가열률로 측정한 글로우 곡선은 5개의 피그들로 분리되었으며, 234℃에 나타나는 주피크의 활성화에너지는 2.34 eV, 진동수인자는 1.00×1023이고, 방출스펙트럼은 410nm를 중심으로한 단일한 분포로 나타났다. 선량의존성은 100Gy 이상까지 선형성을 나타내었으며, 137Cs에 대한 저에너지 광자의 상대적인 에너지 반응값은 20% 범위 이내였다. 또한 실온에서 1년간 보관하였을 때, 시간경과에 따른 TL 감도의 감소가 거의 없는 좋은 페이딩 특성을 보였다. Sintered LiF:Mg,Cu,Na,Si thermoluminescence (TL) pellets were developed for application in radiation dosimetry. In the present study, the TL dosimetric properties of LiF:Mg,Cu,Na,Si TL pellets have been investigated for emission spectrum, dose response, energy response, and fading characteristics. LiF:Mg,Cu,Na,Si TL pellets were made by using a sintering process, that is, pressing and heat treatment from TL powders. Photon irradiations for the experiments were carried out using X-ray beams and a 137Cs gamma source at the Korea Atomic Energy Research Institute(KAERI). The average energies and the dose were in the range of 20-662 keV and 10-6- 102 Gy, respectively. The glow curves were measured with a manual type TLD reader(System 310, Teledyne) at a constant nitrogen flux and a linear heating rate. For a constant heating rate of 5℃·s-1, the main dosimetric peak of glow curve appeared at 234℃, the activation energy was 2.34eV and frequency factor was 1.00×1023. TL emission spectrum is appeared at the blue region centered at 410 nm. A linearity of photon dose response was maintained up to 100 Gy. The photon energy responses relative to 137Cs response were within ±20% at overall photon energy region. The fading of TL sensitivity of the pellets stored at the room temperature was not found for one year.

Li 화합물을 첨가한 CaSO₄:Dy 열중성자 측정용 TLD 소자 개발

양정선,김두영,박재우,김장렬,장시영 제주대학교 방사능이용연구소 2003 연구보고 Vol.17 No.-

Personal neutron dosimetry is quite a difficult area because a neutron is always accompanied with gamma radiation, which is required of a capability for mixed field dosimetry. CaSO₄:Dy phosphor is known to have a very high sensitivity to gamma, but the neutron capture cross section of the constituents of CaSO₄:Dy are so small that the interactions between the thermal neutron and the phosphor are rare. One method to improve the neutron interaction is by introducing an impurity ion with a large thermal neutron captures cross section into the phosphor to act as a neutron target centre such as 6Li. In neutron-gamma mixed radiation fields, if two detectors for the 6Li-7Li compounds embedded CaSO₄:Dy TL pellets are used, a 6Li-compound embedded pellet can detect the neutron and gamma radiation together, and the other pellet can only detect the gamma radiation. Recently Korea Atomic Energy Research Institute (KEARI) has developed a new type of CaSO₄:Dy TL materials embedded with phosphorous (KCT-300) to detect beta and gamma radiation with a very high sensitivity[1]. This paper presents the development of CaSO₄:Dy TL pellets embedded with 6Li compound for a thermal neutron measurement, and the detection method of the neutron and gamma dose in mixed fields with CaSO₄:Dy TL pellets embedded with a 6Li compound(KCT-306) and CaSO₄:Dy TL pellets embedded with a 7Li compound(KCT-307) is introduced. The net neutron sensitivity of CaSO₄:Dy TL pellets embedded with 6Li compound developed in this study is higher than that of the TLD-600 (Harshaw Co.) dosimeter which is available in the open market.

Non-L-cell Immunophenotype and Large Tumor Size in Rectal Neuroendocrine Tumors Are Associated With Aggressive Clinical Behavior and Worse Prognosis

Kim, Joo Young,Kim, Ki-Suk,Kim, Kyung-Jo,Park, In Ja,Lee, Jong Lyul,Myung, Seung-Jae,Park, Yangsoon,Park, Young Soo,Yu, Chang Sik,Kim, Jin Cheon,Yu, Eunsil,Jang, Hyeung-Jin,Hong, Seung-Mo Wolters Kluwer Health, Inc. All rights reserved. 2015 The American journal of surgical pathology Vol.39 No.5

According to the 2010 World Health Organization classification, all gastrointestinal neuroendocrine tumors (NETs) are classified as malignant except for L-cell-type (glucagon-like peptide [GLP] and peptide YY [PYY]-producing) NETs. However, L-cell immunophenotype in rectal NETs has not been widely studied previously. Immunohistochemical labeling of L-cell markers with GLP1 and PYY was performed in 208 surgically or endoscopically resected rectal NET cases with tissue microarrays and was compared with clinicopathologic features and patient survival. Rectal NETs with non-L-cell immunophenotype and large tumor size (>1 cm) were associated with increased tumor grading, advanced T category, lymphovascular and perineural invasions, and lymph node and distant metastases (P<0.001, each). Rectal NET patients with non-L-cell phenotype and measuring >1 cm had significantly worse survival outcome than other groups by univariate (P<0.001) and multivariate (P<0.001) analyses. In summary, non-L-cell immunophenotype and large tumor size are associated with increased tumor grading and staging, concurrently indicating that they are independently poor prognostic indicators in rectal NET patients. Therefore, combining L-cell phenotype and tumor size can demonstrate the clinical behavior of rectal NETs more precisely than use of L-cell immunophenotype alone.

A Theoretical Calculation for Angular Dependence of X-ray Beams on Extremity Phantom

Kim,Jang-Lyul,Yoon,Suk-Chul,Kim,Kwang-Pyo,Kim,Jong-Soo 대한방사선 방어학회 1996 방사선방어학회지 Vol.21 No.4

ANSI N13.32에서는 선량계의 방향에 따른 반응도가 성능시험의 합격판정의 범주는 아니지만 이에 관한 연구를 요구하고 있다. 본 연구에서는 ANSI N13.32의 말단팬텀 즉, 손가락과 손목팬템내의 7㎎/㎠ 깊이에서 MCNP 코드를 사용하여 단일에너지를 가진 광자 및 ISO narrow X-선 빔에 대하여 선량당량환산인자와 방향의존성인자를 도출하였다. X-선 빔에 대하여는 이들 데이터를 B. Grosswent의 연구 결과와 비교하였다. 그 결과 선량당량환산인자는 낮은 에너지영역에서 최대 7%를 그리고 다른 에너지 영역에서는 2% 이내였을며, 방향의존성인자는 최대 3% 정도로 잘 일치하였다. 또한 60keV 이하의 낮은 에너지 영역에서 발생된 방향의존성인자는 손가락 팬텀의 경우에 주축을 따라 수평회전각이 증가할수록 감소하지만 그 에너지 영역 이상에서 90˚까지는 증가하고 있음을 알 수 있었다. The ANSI N13.32 recommends that a study of the angular response of a dosimeter be carried out once, although no pass/fail criterion is given for angular response. Gamma dose equivalent conversion and angular dependence factors were calculated by using MCNP code for the case of ANSI N13.32 extremity phantoms(finger and arm) at the depth of 7㎎/㎠. Those extremity dosimeters were assumed to be irradiated form both monoenergitic photons and ISO X-ray narrow beams. These calculated gamma dose equivalent conversion and angular dependence factors were compared to B. Grosswendt's result calculated by using X-ray beams. The result showed that the dose equivalent conversion factors of this study agreed well with that of B. Grosswendt for all energies within 2% except &% in the case of the low energies. In the case of angular dependence factors comparison, they agreed within 3%. It was shown that angular dependence factors of the finger phantom decreased as the horizontal angle of the phantom increased for the ISO X-ray beams less than 60keV. For the higher energy X-ray beams range they decreased slightly around 40 degree, but then increased from this energy to 90 degree.

Development of Dose Evaluation Algorithm for Film Badge Using ISO Reference Radiations

Kim,Jang-Lyul,Chang,Si-Young,Lee,Jai-Ki 대한방사선 방어학회 1995 방사선방어학회지 Vol.20 No.1

과학기술처의 개인방사선피폭선량평가에 관한 기술기준이 제정된 이후, TLD에 의한 개인피폭선량평가 기술은 많은 발전이 있었으나, 우리나라 대부분의 방사선관련 산업체에서 방사선 피폭관리용으로 사용되고 있는 필름배지의 정확한 선량평가기술을 확보하기 위한 연구는 아직도 미진한 상태이다. 따라서 본 연구에서는 ISO 표준방사선장을 이용하여 ⅰ) 실험식에 의한 방법, ⅱ) Degree-of-fit에 의한 방법, 그리고 ⅲ) Matrix에 의한 방법으로 필름배지에 의한 선량평가 알고리즘 개발방법을 제시하였다. 이러한 방법들에 의한 계산값은 조사량과 ANSI N13.11에서 제시하고 있는 성능지수 이내에서 잘 일치하였으며, 이는 X, γ 혹은 혼합방사선장에서 선량평가에 유용하게 활용될 수 있을 것이다. Since provisions on the technical criteria for personnel dosimetry was amended three years ago, several improvements in the technique of monitoring personnel doses by TLD have taken place, but for the photograpfic film as a personnel monitor, additional investigations should be carried out for its accuracy of dose estimates because of its wide use in the radiation involved industries. So, this paper describes the methods to develop dose evaluation algorithm for photographic film using ISO reference radiations by ⅰ) empirical formula, ⅱ) degree-of-fit method, and ⅲ) matrix approximation. These methods show a good agreement between irradiated and calculated dose within tolerance level represented in ANSI N13. 11, and can be used for the dose evaluation of X, γ and/or mixed radiation fields.

SPECTRUM WEIGHTED RESPONSES OF SEVERAL DETECTORS IN MIXED FIELDS OF FAST AND THERMAL NEUTRONS

Kim, Sang In,Chang, Insu,Kim, Bong Hwan,Kim, Jang Lyul,Lee, Jung Il Korean Nuclear Society 2014 Nuclear Engineering and Technology Vol.46 No.2

The spectrum weighted responses of various detectors were calculated to provide guidance on the proper selection and use of survey instruments on the basis of their energy response characteristics on the neutron fields. To yield the spectrum weighted response, the detector response functions of 17 neutron-measuring devices were numerically folded with each of the produced calibration neutron spectra through the in-house developed software 'K-SWR'. The detectors' response functions were taken from the IAEA Technical Reports Series No. 403 (TRS-403). The reference neutron fields of 21 kinds with 2 spectra groups with different proportions of thermal and fast neutrons have been produced using neutrons from the $^{241}Am$-Be sources held in a graphite pile, a bare $^{241}Am$-Be source, and a DT neutron generator. Fluence-average energy ($E_{ave}$) varied from 3.8 MeV to 16.9 MeV, and the ambient-dose-equivalent rate [$H^*(10)/h$] varied from 0.99 to 16.5 mSv/h.

Calculation of Internal Exposure Dose in Korean Man Resulting from single and Chronic Intake of Tritium

Jang-Lyul Kim,Chong-Chul Yook,Chung-Woo Ha 대한방사선방어학회 1983 방사선방어학회지 Vol.8 No.2

Calculation of Internal Exposure Dose in Korean Man Resulting from Single and Chronic Intake of Tritium

Kim,Jang-Lyul,Yook,Chong-Chul,Ha,Chung-Woo 대한방사선 방어학회 1983 방사선방어학회지 Vol.8 No.2

삼중수소의 단일 피폭과 만성피폭에 의한 한국인의 내부피복 선량을 삼단계형모델을 이용하여 계산하였다. 이 모델은 체내수분과 조직체 사이의 삼중 수소의 축적량을 잘 나타내 주는 것이다. 그 결과 삼단계형의 축적 반감기 9, 30과 450일을 사용한 단일 피폭의 총 선량은 1mCi/kg 섭취당 17.64mrad/day였고 이것의 97%는 체내수분에 있는 삼중수소에 의한 선량이고 나머지 3%는 조직내 삼중수소에 의한 것이다. 그리고 1mCi/day의 삼중 수소를 섭취하는 만성 피폭의 경우, 총 선량은 85.5mrad/day이었다. 또한 본 연구에서는 한국인에 대한 최대허용 농도값을 선질계수 1을 사용하여 계산하였다. 그 결과, ICRP의 최대허용 농도값은 약50%가량 낮게 평가되었으므로 한국인의 최대허용 농도값은 ICRP의 결과보다 약 50%높게 책정되어야만 한다. The doses to Korean adult by a single and chronic intake of tritiated water are determined using a three compartment model, which describes the retention of tritium radionuclidc in body water and in bound organic form in the body. The results show that the total dose of a single intake, using retention half-time for the three-compartment of 9, 30, and 450 days, is 17.64 mrads (176.4 μGy) per ImCi/kg (3.7×10 7Bq/kg) intake, 97% of which is due to tritium in body water and 3% to bound tritium in tissue. In the chronic intake of lmCi/day(3.7×10 7 Bq/day) tritiated water, the total dose is 85.5 mrad/day(0. 855mGy/day). Furthermore, in this study (MPC) a and (MPC)w values of tritium for Korean man are calculated by using the modified formula originated from ICRP Publication-2. From the results, we found that the (MPC) a,w values of ICRP underestimated approximately 50%, the (MPC)a,w values of Korean man must be elevated as high as approximately 50% than that of ICRP.

Comparison Study of Experimental Neutron Room Scattering Corrections with Theoretical Corrections in RCL's Calibration Facility at KAERI

Kim,Bong-Hwan,Kim,Jang-Lyul,Chang,Si-Young,Kim,Jong-Soo,Yoon,Suk-Chul 대한방사선 방어학회 1997 방사선방어학회지 Vol.22 No.1

중성자교정실내에서 D₂O 감속 252Cf중성자선원을 사용하여 계측기를 교정할 때는 그 계측기에 대한 교정실산란정보인자를 미리 결정하여야 한다. 이러한 교정실산란보정인자는 계측기의 종류, 교정거리, 교정실형태에 따라 다르게 결정된다. 본 연구에서는 한국원자력연구소에서 운영하는 2차 표준중성자교정실에서 한가지의 열형광선량계와 2가지의 구형검출기에 대한 교정실산란보정인자를 실험적으로 결정하였고 본소의 2차 표준중성자교정실조건에 의하여 이론적으로 예측한 값과 비교 예측한 비교하였다. 비교한 결과 실험하여 얻어진 상기의 3가지 계측기에 대한 교정실산란정보인자가 이론적으로 예측한 결과와 최대 약 10% 이내에서 일치하였다. Neutron room scattering corrections that should be made when neutron detectors are calibrated with a D₂O moderated 252Cf neutron source in the center of a calibration room are considered. Such room scattering corrections are dependent on specific neutron source type, detector type, calibration distance, and calibration room configuration. Room scattering corrections for the responses of a thermoluminescence dosimeter and two different types of spherical detectors to neutron source in the Radiation Calibration Laboratory (RCL) neutron calibration facility at the Korea Atomic Energy Research Institute(KAERl) were experimentally determined and are presented. The measured room scattering results are then compared with theoretical results calculated by predicting room scattering effects in terms of parameters related to the specific configuration. Agreement between measured and calculated scattering correction is generally about 10% for three kinds of detectors in the calibration facility.