• Title/Summary/Keyword: Radiological Assessment

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Long-Term Clinical and Radiologic Outcomes of Minimally Invasive Posterior Cervical Foraminotomy

  • Kwon, Young-Joon
    • Journal of Korean Neurosurgical Society
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    • v.56 no.3
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    • pp.224-229
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    • 2014
  • Objective : To report long-term clinical and radiological outcomes of minimally invasive posterior cervical foraminotomy (MI-PCF) performed in patients with unilateral single-level cervical radiculopathy. Methods : Of forty-six patients who underwent MI-PCF for unilateral single-level radiculopathy between 2005 and 2013, 33 patients were included in the study, with a mean follow-up of 32.7 months. Patients were regularly followed for clinical and radiological assessment. Clinical outcome was measured by visual analogue scale (VAS) for the neck/shoulder and arm, and the neck disability index (NDI). Radiological outcome was measured by focal/global angulation and disc height index (DHI). Outcomes after MI-PCF were evaluated as changes of clinical and radiological parameters from the baseline. Mixed effect model with random patients' effect was used to test for differences in the clinical and radiological parameters repeat measures. Results : There were no complications and all patients had an uneventful recovery during the early postoperative period. VAS scores for neck/shoulder and arm improved significantly in the early postoperative period (3 months) and were maintained with time (p<0.001). NDI improved significantly post-operatively and tended to decrease gradually during the follow-up period (p<0.001). There were no statistically significant changes in focal and global angulation at follow-up. Percent DHIs of the upper adjacent or operated disc were maintained without significant changes with time. During the follow-up, same site recurrence was not noted and adjacent segment disease requiring additional surgery occurred in two patients (6%) on the contra-lateral side. Conclusion : MI-PCF provides long-term pain relief and functional restoration, accompanied by good long-term radiological outcome.

Development of Internal Dose Assessment Procedure for Workers in Industries Using Raw Materials Containing Naturally Occurring Radioactive Materials

  • Choi, Cheol Kyu;Kim, Yong Geon;Ji, Seung Woo;Koo, Boncheol;Chang, Byung Uck;Kim, Kwang Pyo
    • Journal of Radiation Protection and Research
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    • v.41 no.3
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    • pp.291-300
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    • 2016
  • Background: It is necessary to assess radiation dose to workers due to inhalation of airborne particulates containing naturally occurring radioactive materials (NORM) to ensure radiological safety required by the Natural Radiation Safety Management Act. The objective of this study is to develop an internal dose assessment procedure for workers at industries using raw materials containing natural radionuclides. Materials and Methods: The dose assessment procedure was developed based on harmonization, accuracy, and proportionality. The procedure includes determination of dose assessment necessity, preliminary dose estimation, airborne particulate sampling and characterization, and detailed assessment of radiation dose. Results and Discussion: The developed dose assessment procedure is as follows. Radioactivity concentration criteria to determine dose assessment necessity are $10Bq{\cdot}g^{-1}$ for $^{40}K$ and $1Bq{\cdot}g^{-1}$ for the other natural radionuclides. The preliminary dose estimation is performed using annual limit on intake (ALI). The estimated doses are classified into 3 groups ( < 0.1 mSv, 0.1-0.3 mSv, and > 0.3 mSv). Air sampling methods are determined based on the dose estimates. Detailed dose assessment is performed using air sampling and particulate characterization. The final dose results are classified into 4 different levels ( < 0.1 mSv, 0.1-0.3 mSv, 0.3-1 mSv, and > 1 mSv). Proper radiation protection measures are suggested according to the dose level. The developed dose assessment procedure was applied for NORM industries in Korea, including coal combustion, phosphate processing, and monazite handing facilities. Conclusion: The developed procedure provides consistent dose assessment results and contributes to the establishment of optimization of radiological protection in NORM industries.

Organ Dose Assessment of Nuclear Medicine Practitioners Using L-Block Shielding Device for Handling Diagnostic Radioisotopes (진단용 방사성동위원소 취급 시 L-block 차폐기구 사용에 따른 핵의학 종사자의 장기 선량평가)

  • Kang, Se-Sik;Cho, Yong-In;Kim, Jung-Hoon
    • Journal of radiological science and technology
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    • v.40 no.1
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    • pp.49-55
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    • 2017
  • In the case of nuclear medicine practitioners in medical institutions, a wide range of exposure dose to individual workers can be found, depending on the type of source, the amount of radioactivity, and the use of shielding devices in handling radioactive isotopes. In this regard, this study evaluated the organ dose on practitioners as well as the dose reduction effect of the L-block shielding device in handling the diagnostic radiation source through the simulation based on the Monte Carlo method. As a result, the distribution of organ dose was found to be higher as the position of the radiation source was closer to the handling position of a practitioner, and the effective dose distribution was different according to the ICRP tissue weight. Furthermore, the dose reduction effect according to the L-block thickness tended to decrease, which showed the exponential distribution, as the shielding thickness increased. The dose reduction effect according to each radiation source showed a low shielding effect in proportion to the emitted gamma ray energy level.

Comparison of Echocardiography and Computed Tomography on Cardiac Wall Thickness and Internal Dimension Size of Left Ventricle in Normal Adults (정상 성인의 좌심실 벽두께와 내강 크기에 대한 심초음파영상과 전산화단층영상의 비교)

  • Ji, Myeong-Hoon;Kim, Seoung-Hwan;Seoung, Youl-Hun
    • Journal of radiological science and technology
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    • v.41 no.6
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    • pp.545-552
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    • 2018
  • The purpose of this study was evaluated the relationship between echocardiography and cardiac computed tomography in normal adults by visual assessment, and evaluated the effective doses of cardiac computed tomography. The subjects were 100 normal patients who visited two general hospitals in Chungnam, from January 1 to May 30, 2018. We obtained images by using these modalities and evaluated the wall thickness and internal dimension of the Left Ventricle with visual assessment. To evaluate the appropriateness of the visual evaluation, two evaluators who were trained for one week were measured and the agreement between the evaluators were verified by statistical analysis. The effective doses of computed tomography were evaluated using the dose length product. As a result, there was a high correlation between the two modalities. The agreement between the two visual evaluator were also highly agreed. The mean X-ray dose of the subjects was $11.1{\pm}3.1mSv$. Although the purpose of imaging is somewhat different in the clinical setting, echocardiography could achieve the same results as radiation-invasive computed tomography. It is thought that utilization will become even larger.

Determination of counting efficiency considering the biodistribution of 131I activity in the whole-body counting measurement

  • MinSeok Park ;Jaeryong Yoo;Minho Kim ;Won Il Jang ;Sunhoo Park
    • Nuclear Engineering and Technology
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    • v.55 no.1
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    • pp.295-303
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    • 2023
  • Whole-body counters are widely used to assess internal contamination after a nuclear accident. However, it is difficult to determine radioiodine activity due to limitations in conventional calibration phantoms. Inhaled or ingested radioiodine is heterogeneously distributed in the human body, necessitating time-dependent biodistribution for the assessment of the internal contamination caused by the radioiodine intake. This study aims at calculating counting efficiencies considering the biodistribution of 131I in whole-body counting measurement. Monte Carlo simulations with computational human phantoms were performed to calculate the whole-body counting efficiency for a realistic radioiodine distribution after its intake. The biodistributions of 131I for different age groups were computed based on biokinetic models and applied to age- and gender-specific computational phantoms to estimate counting efficiency. After calculating the whole-body counting efficiencies, the efficiency correction factors were derived as the ratio of the counting efficiencies obtained by considering a heterogeneous biodistribution of 131I over time to those obtained using the BOMAB phantom assuming a homogeneous distribution. Based on the correction factors, the internal contamination caused by 131I can be assessed using whole-body counters. These correction factors can minimize the influence of the biodistribution of 131I in whole-body counting measurement and improve the accuracy of internal dose assessment.

A Study on Mice Exposure Dose for Low-dose Gamma-irradiation Using Glass Dosimeter (유리선량계를 이용한 저선량 방사선의 마우스 피폭선량 연구)

  • Noh, Sung Jin;Kim, Hyo Jin;Kim, Hyun;Jeong, Dong Hyeok;Son, Tae Gen;Kim, Jung Ki;Yang, Kwangmo;Nam, Sang-Hee;Kang, Yeong-Rok
    • Journal of Radiation Protection and Research
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    • v.40 no.4
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    • pp.202-210
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    • 2015
  • The low dose radiation is done for a long period, thus researchers have to know the exact dose distribution for the irradiated mouse. This research has been conducted in order to find out methods in transmitting an exact dose to mouse in a mouse irradiation experiment carried out using $^{137}Cs$ irradiation equipment installed in the DIRAMS (Dongnam Institution of Radiological & Medical Sciences) research center. We developed a single mouse housing cage and shelf with adjustable geometric factors such as distance and angle from collimator. The measurement of irradiated dose showed a maximal 42% difference of absorbed dose from the desired dose in the conventional irradiation system, whereas only 6% difference of the absorbed dose was measured in the self-developed mouse apartment system. In addition, multi mice housing showed much difference of the absorbed dose in between head and body, compared to single mouse housing in the conventional irradiation system. This research may allow further research about biological effect assessment for the low dose irradiation using the self-developed mouse apartment to provide more exact doses which it tries to transmit, and to have more reliability for the biological analysis results.

Development of Self-Questionnaire for Internal Dose Assessment by Food Ingestion

  • JiEun Lee;Hyo Jin Kim;Yong-Uk Kye;Dong-Yeon Lee;Wol Soon Jo;Chang-Geun Lee;Jung-Ki Kim;Yeong-Rok Kang
    • Journal of Radiation Protection and Research
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    • v.47 no.4
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    • pp.204-213
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    • 2022
  • Background: The accident at the Fukushima Daiichi nuclear power plant increased the level of anxiety related to the radioactive contamination of various foods sourced in Japan. Particularly, after the accident, the detection of artificial radionuclides in locally produced foods raised food safety concerns. In this study, the radioactivity concentrations and annual ingestions of 40K and 137Cs in food products commonly and frequently consumed by the general public were investigated, and the annual effective dose of each was evaluated. Materials and Methods: The 2016-2018 data from the Radiation Safety Management Report released by the Korea Nuclear Safety Technology Center was referenced for the evaluation of the amounts of 40K and 137Cs contained in food. Using the food-ingestion survey mentioned above as a reference, we selected 62 foods to include in our radioactivity concentration and dose assessment. We also developed a questionnaire and evaluated the responses from the subjects who answered the questionnaire. Results and Discussion: The radioactivity concentration of 137Cs was found to be close to or below the level of minimum detectable activity. Additionally, the annual ingestion of 62 foods was 294.77 kg/yr, the effective doses from 40K and 137Cs were 136.4 and 0.163 μSv/yr, respectively. Conclusion: Thus, the findings confirmed that the effective dose from 40K and 137Cs in food tends to be lower than the effective dose limit of 1 mSv/yr suggested by the International Commission on Radiological Protection (ICRP) Publication 60. The questionnaire developed in this study is expected to be useful for estimating the annual effective dose status of Korean adults who consume foods containing 40K and 137Cs.

A Study on the Food Consumption Rates for Off-site Radiological Dose Assessment around Korean Nuclear Power Plants (국내 원자력발전소 주변 주민의 방사선량 평가를 위한 음식물 섭취율 설정 연구)

  • Lee, Gab-Bock;Chung, Yang-Geun
    • Journal of Radiation Protection and Research
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    • v.33 no.4
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    • pp.183-196
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    • 2008
  • The internal dose by food consumption mostly accounts for radiological dose of public around nuclear power plants (NPPs). But, food consumption rates applied to off-site dose calculation in Korea which are the result of field investigation around Kori NPP by the KAERI (Korea Atomic Energy Research Institute) in 1988, are not able to reflect the latest dietary characteristics of Korean. The food consumption rates to be used for radiological dose assessment in Korea are based on the maximum individual of US NRC (Nuclear Regulatory Commssion) Regulatory Guide 1.109. However, the representative individual of the critical group is considered in the recent ICRP (International Commission on Radiological Protection) recommendation and European nations' practice. Therefore, the study on the re-establishment of the food consumption rates for individual around nuclear power plant sites in Korea was carried out to reflect on the recent change of the Korean dietary characteristics and to apply the representative individual of critical group to domestic regulations. The Ministry of Health and Welfare Affairs has investigated the food and nutrition of nations every 3 years based on the Law of National Health Improvement. The statistical data such as mean, standard deviation, various percentile values about food consumption rates to be used for the representative individual of the critical group were analyzed by using the raw data of the national food consumption survey in $2001{\sim}2002$. Also, the food consumption rates for maximum individual are re-estimated.