• Title/Summary/Keyword: Radiological Safety

Search Result 538, Processing Time 0.028 seconds

Endoscopic management of postoperative bleeding

  • Sung Hyeok Ryou;Ki Bae Bang
    • Clinical Endoscopy
    • /
    • v.56 no.6
    • /
    • pp.706-715
    • /
    • 2023
  • Postoperative gastrointestinal bleeding is a rare but serious complication that can lead to prolonged hospitalization and significant morbidity and mortality. It can be managed by reoperation, endoscopy, or radiological intervention. Although reoperation carries risks, particularly in critically ill postoperative patients, minimally invasive interventions, such as endoscopy or radiological intervention, confer advantages. Endoscopy allows localization of the bleeding focus and hemostatic management at the same time. Although there have been concerns regarding the potential risk of creating an anastomotic disruption or perforation during early postoperative endoscopy, endoscopic management has become more popular over time. However, there is currently no consensus on the best endoscopic management for postoperative gastrointestinal bleeding because most practices are based on retrospective case series. Furthermore, there is a wide range of individual complexities in anatomical and clinical settings after surgery. This review focused on the safety and effectiveness of endoscopic management in various surgical settings.

A Study on Development of Guideline on Writing Technical Document for Electrical Medical Devices : Bone Absorptiometric X-ray System (엑스선골밀도측정기의 기술문서 작성을 위한 가이드라인 개발 연구)

  • Lee, Seung-Youl;Kim, Jae-Ryang;Kim, Eun-Rim;Lee, Jun-ho;Lee, Chang-Hyung;Park, Chang Won
    • Journal of radiological science and technology
    • /
    • v.39 no.2
    • /
    • pp.263-271
    • /
    • 2016
  • The market size of the bone absorptiometric X-ray system and the number of its approval by Ministry of Food and Drug Safety (MFDS) has annually increased, with a trend of increasing aging population and osteoporosis patients. For approval of manufactured or imported medical devices in Republic of Korea, it is required to submit its technical document. Therefore, it is need to develop the technical document guideline for the bone absorptiometric X-ray system for manufacturers, importers and reviewers. First of all, the technical documents which were already approved were examined and analyzed through MFDS approval administration system. Second, safety and performance test standards and methods that match international standards were drawn after conducting survey of the market status and the technology development trend for it, with examination and analysis of applicable domestic and overseas standards. Third, by operating industry-research-government cooperation, the guideline draft on writing technical document for the bone absorptiometric X-ray system was discussed, collecting their opinion. As a result, it is suitable to international and domestic condition, includes test evaluation methods and offer various information with appropriate examples to civil petitioner, when they write the technical documents.

Suggestion of Risk Assessment Methodology for Decommissioning of Nuclear Power Plant (원자력발전소 해체 위험도 평가 방법론 개발)

  • Park, ByeongIk;Kim, JuYoul;Kim, Chang-Lak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.17 no.1
    • /
    • pp.95-106
    • /
    • 2019
  • The decommissioning of nuclear power plants should be prepared by quantitative and qualitative risk assessment. Radiological and non-radiological hazards arising during decommissioning activities must be assessed to ensure the safety of decommissioning workers and the public. Decommissioning experiences by U.S. operators have mainly focused on deterministic risk assessment, which is standardized by the U.S. Nuclear Regulatory commission (NRC) and focuses only on the consequences of risk. However, the International Atomic Energy Agency (IAEA) has suggested an alternative to the deterministic approach, called the risk matrix technique. The risk matrix technique considers both the consequence and likelihood of risk. In this study, decommissioning stages, processes, and activities are organized under a work breakdown structure. Potential accidents in the decommissioning process of NPPs are analyzed using the composite risk matrix to assess both radiological and non-radiological hazards. The levels of risk for all potential accidents considered by U.S. NPP operators who have performed decommissioning were estimated based on their consequences and likelihood of events.

Effect of Field Size on the Clinical Exposure Index for Lumbar Spine X-ray Examination (노출지수를 이용한 요추 X선 촬영의 조사야 유효성 평가)

  • Park, Hyemin;Yoon, Yongsu;Kim, Jungsu;Jeong, Hoiwoun
    • Journal of radiological science and technology
    • /
    • v.44 no.3
    • /
    • pp.183-187
    • /
    • 2021
  • The field size of the lumbar spine X-ray examination, which belongs to the most frequent examination in general radiography, is 5 times wider than the width of the lumbar spine. Exposure index (EI) as per International Electrotechnical Commission has a proportional relationship with the dose incident on the image receptor for clinical protocols in addition to RQA5, which is a calibration beam quality. In this study, the effectiveness of the set field size was evaluated through the change of EI according to the size of field during lumbar spine X-ray examinations. Lumbar anterior-posterior and lateral examinations was performed using a whole-body phantom, and the national average exposure conditions of Korea investigated in 2017 were introduced for the X-ray exposure. As a result of comparing the EI displayed on the console of digital radiography system for the three field size in ① 18 × 36 cm2 ② 25 × 36 cm2 ③ 36 × 36 cm2, the EI values showed a tendency to increase as the field size increased. Since the patient dose, such as organ dose around the lumbar spine, increases as the field size becomes larger, thus, if the EI obtained from the field size at a level that does not interfere with diagnosis is set as a reference, the effectiveness of the field size can be evaluated through the EI displayed on the console when the lumbar spine X-ray examination is conducted.

Personal Dosimeters Worn by Radiation Workers in Korea: Actual Condition and Consideration of Their Proper Application for Radiation Protection

  • Eunbi Noh;Dalnim Lee;Sunhoo Park;Songwon Seo
    • Journal of Radiation Protection and Research
    • /
    • v.48 no.3
    • /
    • pp.162-166
    • /
    • 2023
  • Background: Assessment of the radiation doses to which workers are exposed can differ depending on the placement of dosimeters on the body. In addition, it is affected by whether the placement is under or over a shielding apron. This study aimed to evaluate the actual positioning of personal dosimeters on the body, with or without shielding aprons, among radiation workers in Korea. Materials and Methods: We analyzed the survey data, which included demographic characteristics, such as sex, age, occupation, work history, and placement of the personal dosimeter being worn, from a cohort study of Korean radiation workers. We assessed the use of personal dosimeters among workers, stratified by sex, age, working period, starting year of work, and occupation. Results and Discussion: Overall, high compliance (89.1% to 99.0%) with the wearing of dosimeters on the chest was observed regardless of workers' characteristics, such as age, sex, occupation, and work history. However, the placement of dosimeters, either under or over the shielding aprons, was inconsistent. Overall, 40.1% of workers wore dosimeters under their aprons, while the others wore dosimeters over their aprons. This inconsistency indicates that radiation doses are possibly measured differently under the same exposure conditions solely owing to variations in the placement of worn dosimeters. Conclusion: Although a lack of uniformity in dosimeter placement when wearing a shielding apron may not cause serious harm in radiation dose management for workers, the development of detailed guidelines for dosimeter placement may improve the accuracy of dose assessment.

An Integrative Review on Domestic Site Release Criteria of Nuclear Power Plant based on the Analysis of Foreign Site Release Criteria (국외 부지해제기준 분석을 통한 국내 원자력발전소 부지해제기준 도출에 관한 고찰)

  • Bae, YuJung;Kim, Yongmin;Ahn, Seokyoung;Kim, Cheol Min
    • Journal of the Korean Society of Radiology
    • /
    • v.9 no.5
    • /
    • pp.269-277
    • /
    • 2015
  • In recent years, concern about the decommissioning of nuclear power plants has been growing according to the nuclear power plants aging. Although site reuse is one of the most important issues in doing decommissioning of nuclear power plants in view of the internal affairs, there is currently no specific standard of the site release criteria for site reuse in the Republic of Korea. In this study, we analyzed the international safety standards for the site release(IAEA's Safety Guide No. WS-G-5.1) and the present domestic condition. Also, we studied the site release criteria and real life examples about advanced countries such as United states and Europe, which already have experience of decommissioning or site release. As a results of the study, we suggested proper standards and future consideration to establish site release criteria. This will be used for preliminary data for establishing the domestic site release criteria after the decommissioning of nuclear power plants.

Safety Assessment on the Incineration Disposal of Regulation Exempt Waste by RESRAD Code (RESRAD 코드를 활용한 규제해제 폐기물 소각처분에 대한 안정성 평가)

  • Kim, Hui-Gyeong;Han, Sang-Wook;Park, Su-Ri;Kim, Byung-Jick
    • Journal of radiological science and technology
    • /
    • v.41 no.1
    • /
    • pp.67-73
    • /
    • 2018
  • In this paper, risk assessment was conducted to verify self - disposal requirements by landfill for exempted incineration ash by using Resrad Ver.6.5 computer code. The result of risk assessment by landfill for the incineration by-product is that individual dose is $6.91{\times}10^{-2}{\mu}Sv\;y-1$ and collective dose is $3.475{\times}10^{-7}man-Sv\;y-1$. It proved that the result meets reference dose of individual dose $10{\mu}Sv\;y-1$ and collective dose 1 man-Sv y-1 for general public. According to the current 'Nuclear Safety Commission Notice [No. 2014-3]', it states that the exempted wastes can be disposed of by incineration, landfill and recycling. However, most of recently documents and papers related to exempted wastes are disposed of by landfill and recyling and it could not confirm the case of exempt by incineration. If the national consensus is derived and treating the waste by using process of incineration is activated, it could be considered to treat low level of radiation wastewater and activated carbon excluded from exempted waste because of nuclide $^3H$ and $^{14}C$.

A Study on the Measurement Linearity of Photoluminescent Dosimeter (형광유리선량계의 계측 직선성 연구)

  • Jeong, Kyeong-Hwan;Jung, Dong-Kyung;Seo, Jeong-Min
    • Journal of the Korean Society of Radiology
    • /
    • v.15 no.6
    • /
    • pp.841-847
    • /
    • 2021
  • Related institutions that use radiation are diverse in Korea, such as research, medical care, and education. Recently, the number of examinations and visits to medical institutions is increasing. As a result, the number of radiological examinations in medical institutions is increasing. Radiation safety management is necessary as well as exposure of radiation workers. For safety management, first of all, it is necessary to wear the personal exposure dosimeter correctly and measure it accurately after wearing it. This study tries to evaluate and verify the measurement straightness of PLD devices by radiation of a diagnostic generator. Radiation division irradiation time interval was measured after irradiating 10 times at 10, 30, and 60 sec and irradiating the irradiation distance from 30 to 100 cm at 10 cm intervals to measure the change in absorbed dose depending on the distance. As a result, there was no difference in absorbed dose by time interval. This is considered to be helpful in various studies by using a diagnostic generator for the study of high absorbed dose.

Verification of Harmonization of Dose Assessment Results According to Internal Exposure Scenarios

  • Kim, Bong-Gi;Ha, Wi-Ho;Kwon, Tae-Eun;Lee, Jun-Ho;Jung, Kyu-Hwan
    • Journal of Radiation Protection and Research
    • /
    • v.43 no.4
    • /
    • pp.143-153
    • /
    • 2018
  • Background: The determination of the amount of radionuclides and internal dose for the worker who may have intake of radionuclides results in a variation due to uncertainty of measurement data and ingestion information. As a result of this, it is possible that for the same internal exposure scenario assessors could make considerably different estimation of internal dose. In order to reduce this difference, internal exposure scenarios for nuclear facilities were developed, and intercomparison were made to determine the harmonization of dose assessment results among the assessors. Materials and Methods: Seven cases on internal exposures incidents that have occurred or may occur were prepared by referring to the intercomparison excercise scenario that NRC and IAEA have carried out. Based on this, 16 nuclear facilities concerned with internal exposure in Korea were asked to evaluate the scenarios. Each result was statistically determined according to the harmonization discrimination criteria developed by IDEAS/IAEA. Results and Discussion: The results were evaluated as having no outliers in all 7 cases. However, the distribution of the results was spread by various causes. They can be divided into two wide categories. The first one is the distribution of the results according to the assumption of the intake factors and the evaluation factors. The second one is distribution due to misapplication of calculation method and factors related to internal exposure. Conclusion: In order to satisfy the harmonization criteria and accuracy of the internal exposure dose evaluation, it is necessary that exact guidelines should be set on low dose, and various intercomparison cases also be needed including high dose exposure as well as the specialized education. The aim of the blind test is to make harmonization evaluation, but it will also contribute to securing the expertise and high quality of dose evaluation data through the discussion among the participants.

Estimation of Appropriate Number of Radiologic Technologist Based on Analysis of Time Required for Computed Tomography (전산화단층촬영의 소요시간 분석에 기반한 방사선사의 적정인력 산정에 관한 연구)

  • Lee, Ki-Baek;Kim, Yung-Kyoon;Kim, Eun-Hye;Kim, Yon-Min
    • Journal of radiological science and technology
    • /
    • v.45 no.3
    • /
    • pp.213-223
    • /
    • 2022
  • Although the number of computed tomography(CT) is increasing every year, it is insufficient to establish appropriate workload calculation standards of radiologic technologist to provide optimal medical services to patients, such as patient safety management and infection management. The purpose of this study is to present guidelines for calculating the appropriate workload of radiologic technologist by analyzing the work flow of CT procedures and the time required for CT examination in major hospitals. As for the study subjects and methods, the appropriate process for each step of CT examination was investigated to systematically present the process and time required for the actual examination, and the CT procedure time of 104,105 adult patients and 465 pediatric patients under the age of 6 were analyzed. For the time required, data according to the use of contrast medium, procedure type, and adult/child were collected and compared. The test time of CT examination using contrast medium took about 13 minutes when one radiologic technologist worked and about 9 minutes when two radiologic technologists worked. The time required for the procedures were statistically significant depending on the presence or absence of contrast medium, multi-phase procedure, and patient age (considering pediatric patients). As a result, in order to thoroughly perform patient safety and infection management, the appropriate workload increased by about 40% when there were two radiologic technologists. The limit workload was an average of 32 people per day with one radiologic technologist per 15 minutes, and 48 people per day with two radiologic technologist per 10 minutes. This is a marginal workload, and in the case of procedures that require more time to acquire radiographic images, the interval between reservations should be widened.