• Journal of radiological science and technology
• /
• v.28 no.2
• /
• pp.117-122
• /
• 2005

According to the Para. 5 of Art 2 of the Korean Nuclear Safety Regulations, which was revised in 1999, internal dose assessment as well as external one should be performed by law for employees at a nuclear power plant from 2003, and their estimate errors should also be within 50%. Thus, more accurate internal dosimetry becomes important. Corresponding to such regulation revision, we are developing a more accurate thyroid-uptake internal dosimetric system and have developed a Monte Carlo simulation code, the so-called CALEFF, to calculate the detection efficiency of the dosimetric system. In this paper, we calculated detection efficiencies with various test conditions by using the CALEFF code and discussed their characteristics. We may use the detection efficiency calculated by the code in calibrating the thyroid internal dose from measured data.

• Progress in Medical Physics
• /
• v.24 no.4
• /
• pp.253-258
• /
• 2013

The purpose of this study is to evaluate and analyze the relationship between the external radiation dose reconstruction which is transmitted from the patient who receives radiation treatment through electronic portal imaging device (EPID) and the internal dose derived from the Monte Carlo simulation. As a comparative analysis of the two cases, it is performed to provide a basic indicator for similar studies. The geometric information of the experiment and that of the radiation source were entered into Monte Carlo n-particle (MCNPX) which is the computer simulation tool and to derive the EPID images, a tally card in MCNPX was used for visualizing and the imaging of the dose information. We set to source to surface distance (SSD) 100 cm for internal measurement and EPID. And the water phantom was set to be 100 cm of the source to surface distance (SSD) for the internal measurement and EPID was set to 90 cm of SSD which is 10 cm below. The internal dose was collected from the water phantom by using mesh tally function in MCNPX, accumulated dose data was acquired by four-portal beam exposures. At the same time, after getting the dose which had been passed through water phantom, dose reconstruction was performed using back-projection method. In order to analyze about two cases, we compared the penetrated dose by calibration of itself with the absorbed one. We also evaluated the reconstructed dose using EPID and partially accumulated (overlapped) dose in water phantom by four-portal beam exposures. The sum dose data of two cases were calculated as each 3.4580 MeV/g (absorbed dose in water) and 3.4354 MeV/g (EPID reconstruction). The result of sum dose match from two cases shows good agreement with 0.6536% dose error.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2003.11a
• /
• pp.579-583
• /
• 2003

This study was to compare the Intake and Committed Effective Dose(CED) due to inhalation of I-131. The Intake and CED Calculations were based on KIDAC, LUDEP, MONDAL and IMBA computer codes.

• Journal of Radiation Protection and Research
• /
• v.34 no.1
• /
• pp.37-42
• /
• 2009

Whole body counters (WBCs) are used to monitor radiation workers for internal contamination of radionuclides at domestic nuclear power plants (NPPs). A WBC is a scintillation detector using sodium iodide (NaI) and provides the identification of inhaled radionuclide and the measurement of its internal radioactivity in a short time. However, it is often possible to estimate external contamination as internal contamination due to radionuclides attached to the skin of radiation workers and this leads to an excessively conservative estimation of radioactive contamination. In this study, several experiments using a WBC and the Korean humanoid phantom were performed to suggest the more systematic method of discrimination between external and internal contamination. Furthermore, a WBC geometry experiment was conducted to suggest the optimal WBC geometry in consideration of deposited areas inside the body for dominant radionuclides at NPPs. The procedure of measurement and estimation of internal radioactivity for radiation workers at NPPs was improved on the basis of experimental results. Thus, it is expected to prevent from estimating internal exposure dose conservatively owing to the application of accurate whole body counting program to NPPs.

• 대한방사선방어학회:학술대회논문집
• /
• 2009.11a
• /
• pp.96-97
• /
• 2009

• 대한방사선방어학회:학술대회논문집
• /
• 2010.04a
• /
• pp.110-111
• /
• 2010

• Journal of Radiation Protection and Research
• /
• v.34 no.3
• /
• pp.129-136
• /
• 2009

During the maintenance period at Korean nuclear power plants, internal exposure of radiation workers occurred by the inhalation of $^{131}I$ released to the reactor building when primary system opened. The internal radioactivity of radiation workers contaminated by $^{131}I$ was measured using a whole body counter. Intake estimation and the calculation of committed effective dose were also conducted conforming to the guidance of internal dose assessments from publications of International Commission on Radiological Protection. Because the uptake and excretion of $^{131}I$ in a body occur quickly and $^{131}I$ is accumulated in the thyroid gland, the estimated intakes showed differences depending on the counting time after intake. In addition, since ICRP publications do not provide the intake retention fraction (IRF) for whole body of $^{131}I$, the IRF for thyroid was substitutionally used to calculate the intake and subsequently this caused more error in intake estimation. Thus, intake estimation and the calculation of committed effective dose were conducted by manual calculation. In this study, the IRF for whole body was also calculated newly and was verified. During this process, the estimated intake and committed effective dose were reviewed and compared using several computer codes for internal dosimetry.

• 대한방사선방어학회:학술대회논문집
• /
• 2009.11a
• /
• pp.188-189
• /
• 2009

• Journal of Radiation Protection and Research
• /
• v.2 no.1
• /
• pp.38-46
• /
• 1977

오늘날 에너지 공급(供給)을 위한 새로운 해결책(解決策)의 하나로서 등장(登場)한 원자력발전소(原子力發電所), 재래(在來)의 X선(線) 진료(診療) 이외(以外)에 의학계(醫學界)에 도입(導入)된 방사선원(放射線源), 그리고 각종(各種) 전자생산품(電子生産品) 등(等)의 증가현상(增加現象)은 방사선(放射線) 방어(防禦) 문제(問題)와 관련(關聯)하여 보건의학분야(保健醫學分野)에서 종사(從事)하는 사람들에게 지대(至大)한 관심(關心)거리가 되고있다. 그래서, 우선(于先) 방사선(放射線)에 관(關)한 사항(事項)중에서 가장 기초(基礎)가되는 방사선량계측(放射線量計測)에 있어서 그 양(量)과 단위(單位) 문제(問題)가 체계적(體系的)으로 서술(敍述)되었다. 즉(卽) 방사선(放射線)이 인체(人體)에 끼칠 수 있는 해(害)로운 영향(影響)에 그 주안점(主眼點)을 두어 조사선량(照射線量), 흡수선량(吸收線量), 선량당량(線量當量), 그리고 그들의 관계(關係) 및 방사능등(放射能等)에 관(關)하여 토론(討論)되었다. 특(特)히 조사선량률(放射線量率), X는 비(比)감마선선상수(線常數), ($\Gamma$)를 포함(包含)하는 함수(函數)로 표현(表現)되었고, 끝으로 인체(人體) 내부(內部)에 축적(蓄積)된 방사능(放射能)으로부터의 영향(影響)에 의(依)한 이른바 생물학적효과(生物學的效果) (Somatic or Genetic Effects)와 관련(關聯)되는 내부흡수선량율(內部吸收線量率)은 평형흡수선량상수(平衡吸收線量常數)($\Delta_i$)와 흡수율($F_i$)를 포함(包含)하는 수학적(數學的) 모델로 소개(紹介)되었다. 한편 방사능(放射能)은 방사선원(放射線源) 물질(物質)의 자연붕괴율(自然崩壞率)이므로 다른 방사선량(放射線量)들 즉(卽) 조사선량(照射線量), 흡수선량(吸收線量)그리고 선량당량(線量當量)과는 별도(別途)로 취급(取扱)하였음을 부언(附言)한다.

• Journal of Radiation Protection and Research
• /
• v.37 no.4
• /
• pp.226-230
• /
• 2012

The gross alpha analysis of nasal smear samples for the radiation emergency and the additional follow-up steps were established. Cotton swab sticks using in local hospitals for nasal smear in Korea were used for the verification. The measurement results of standard samples spiked with certified reference source were well agreed within ${\pm}20%$ compared with reference values. The clearance ratio of smear samples conducted with wet smear condition showed higher value. To eliminate the quenching effect of liquid scintillation samples, dry of smear samples should be followed up before counting samples. Based on the measurement results, medical decision levels and internal dose assessment were established for the victims in the beginning of radiation emergency.