• 제목/요약/키워드: I-131 therapy ward

검색결과 5건 처리시간 0.018초

131I 치료입원실 폐기물 방사능 오염도 분석 및 자체처분가능일자 산출 (Determination of Self-Disposal date by the Analysis of Radioactive Waste Contamination for 1131I Therapy Ward)

  • 김기섭;정해조;박민석;정진성
    • 핵의학기술
    • /
    • 제17권1호
    • /
    • pp.3-6
    • /
    • 2013
  • Purpose: The treatment of thyroid cancer patients was continuously increased. According to the increment of thyroid cancer patients, the establishment of iodine therapy site was also increased in each hospital. This treatment involves the administration of radioactive iodine, which will be given in the form of a capsule. Therefore, protections and managements for radioactive source pollution and radiation exposure should be necessary for radiation safety. Among the many problems, the problem of disposing the radioactive wastes was occurred. In this study, The date for self-disposal for radioactive wastes, which were contaminated in clothes, bedclothes and trash, were calculated. Materials and Methods: The number of iodine therapy ward was 15 in Korea Institute of Radiological Medical and Sciences. Recently, 8 therapy wards were operated for iodine therapy patients and others were on standby for emergency treatment ward of any radiation accidents. Radioactive wastes, which were occurred in therapy ward, were clothes, bedclothes, bath cover for patients washing water and food and drink which was leftover by patients. Each sample was hold into the marinelli beaker (clothes, bedclothes, bath covers) and 90 ml beaker (food, drink, and washing water). The activities of collected samples were measured by HpGe MCA device (Multi Channel Analysis, CANBERRA, USA) Results: The storage period for the each kind of radioactive wastes was calculated by equation of storage periods based on the measurement outcomes. The average storage period was 60 days for the case of clothes, and the maximum storage period was 93 days for patient bottoms. The average storage period and the maximum storage period for the trash were 69 days and 97 days, respectively. The leftover foods and drinks had short storage period (the average storage period was 25 days and maximum storage period was 39 days), compared with other wastes. Conclusion: The proper storage period for disposing the radioactive waste (clothes, bedclothes and bath cover) was 100 days by the regulation on self-disposal of radioactive waste. In addition, the storage period for disposing the liquid radioactive waste was 120 days. The current regulation for radioactive waste self-disposing was not suitable for the circumstances of each radioactive therapy facility. Therefore, it was necessary to reduce the leftover food and drinks by adequate table setting for patients, and improve the process and regulation for disposing the short-half life radioactive wastes.

  • PDF

방사성 요오드 치료 후, 퇴원 선량 측정에 있어 각국의 기준 및 권고 비교 (The Study on the Dilution Time of Radioactive Tracer in Estradiol Measurement)

  • 이승재;서수현;이성하;박용성;오기백;김재삼
    • 핵의학기술
    • /
    • 제21권2호
    • /
    • pp.49-54
    • /
    • 2017
  • Purpose The high-dose administration of I-131 has been standing for the basic therapy method of thyroid cancer. In korea, it is not necessary for patients to be hospitalized if the administration dose are under 1.2 GBq. However, if the dose are over 1.2 GBq, the patients should be stay in special ward with radiation shield. In such cases, the radioactivity level upon release should be under a dose of $70{\mu}Sv/hr$ at a distance of approx. 1m. This regulation bring the patients to stay for about 2 to 3 days in ward before the release. Materials and Methods Using the inpatients' release data of severance hospital, an inpatient-days were retrospectively calculated and compared with practical data and estimate the inpatient-days with the conditions of korea ($70{\mu}Sv/hr$), Japan ($30{\mu}Sv/hr$), germany ($3.5{\mu}Sv/hr$ at a distance of approx. 2 m), and other european countries. Results When a effective half-life of 15.4 was used, the expected inpatient-days were calculated as 2.15 days in the condition of Japanese regulation and 1.37 days in the condition of korean regulation. The practical inpatient-days of patients in Severance hospital were 1.32 days. Conclusion As ICRP 94 has been mentioned that the release of patients administrated with I-131 for the therapy should be carefully considered because each patients has different thyroid uptake rate and their conditions with family members after the release from the ward. Nonetheless, efforts to bring more aquate data which is for getting closer to the practical data should be continuously studied.

  • PDF

치료병실에서 배출되는 방사성오염 폐기물의 처리 방안 (Radioactive Waste Management Procedure of Thyroid Cancer Patients in Isolation room)

  • 정석;오기백;박훈희;김재삼;이창호
    • 핵의학기술
    • /
    • 제12권1호
    • /
    • pp.119-122
    • /
    • 2008
  • Radioiodine (I-131) Therapy has been known one of the methods treated with hyperthyroidism and thyroid tumor, using a separate ward. This technique has been already used for several decades, and its clinical efficacy proven. Today, Radioiodine takes a form of capsule through continuous development, so, 30 odd domestic hospitals run about 63 separate wards. And, its demands would increase continuously; because of tending upwards the patients had thyroid cancer. However, various kinds of wastes originate from a procedure of radioiodine therapy. Especially, when their radioactivity exceed permissible level (4 Bq/$cm^2$) set by Nuclear laws of the Republic of Korea, it regards as radioactive wastes, then, managed separately from origination to the last disposal.

  • PDF

I-131 치료시 환자의 신장기능과 다양한 요인으로 의한 퇴원선량 및 치료병실 오염도의 유의성에 관한 연구 (In the Treatment I-131, the Significance of the Research that the Patient's Discharge Dose and Treatment Ward can Affect a Patient's Kidney Function on the Significance of Various Factors)

  • 임광석;최학기;이기현
    • 핵의학기술
    • /
    • 제17권1호
    • /
    • pp.62-66
    • /
    • 2013
  • 우리나라의 갑상선 암이 증가함에 따라서 갑상선 전 절제술 후 고용량 방사성동위원소 치료를 받는 환자 또한 증가하였다. 하지만 치료를 위해서 사용되는 I-131의 경우 반감기가 8.01일 이며 감마선과 베타선을 내는 특징이 있어 타인에게 줄 수 있는 외부 피폭의 영향을 막기 위해 일정기간 동안 환자가 격리병실에 입원하여 치료를 받게 된다. 이틀 내지 사흘 동안의 격리치료를 한 후 퇴원 전 환자의 몸에서 나오는 방사선량이 법적 기준(70 uSv/h)에 만족하는지 확인한 후 퇴원을 하게 된다. 그리고 다음 환자가 입원 시까지 병실 곳곳의 오염도를 확인 한 후 필요 시에는 제염작업을 수행하게 된다. 우리는 이러한 일련의 과정들 상에서 의료진들이 피폭의 영향을 받게 되는 주 요인으로는 환자의 퇴원선량 확인 및 치료병실의 오염도확인과 제염작업시의 피폭으로 예상된다. 본 연구는 환자의 여러 가지 요소들을(환자의 신기능, 연령, 성별, 초기 투여용량, Tg, Tg-ab)정하고 그 인자들을 통해 환자의 퇴원선량 및 치료병실 오염도에 어떠한 영향을 미치는지 알아보고자 한다. 본원에서 2011년 8월 1일부터 2012년 5월 29일까지 입원하여 고용량방사성 요오드 치료를 받은 환자 151명을 대상으로 실시하였다. 환자의 glomerular filtration rate (GFR) 값이 높을수록 퇴원선량이 낮은 상관관계를 보였다(P<0.001).초기 투여용량의 경우 5.5 GBq (150 mCi) 미만과 5.5 GBq (150 mCi) 이상을 투여 받은 환자군 두 그룹 사이에 평균 퇴원선량을 비교 분석한 결과 5.5 GBq (150 mCi) 미만을 투여 받은 환자 군에서 퇴원선량이 유의하게 낮음을 알 수 있었다($23.95{\pm}10.44uSv/h$, $28.65{\pm}11.79uSv/h$). 연령,성별, Tg, Tg-ab는 환자의 퇴원 선량과 유의한 관계를 보이지 않았다(p>0.05). 그리고 치료병실 오염도는 환자의 퇴원선량과 환자의 신기능과는 유의한 관계를 보이지 않았다 (p>0.05). 병실 오염도의 경우는 입원기간 동안 환자의 생활습관이나 기타 다른 다양한 요인에 의해 영향을 받을 것으로 사료된다. 비록 성별의 집단 간에 따라서 오차가 있다고 여겨지지만 추후 더 많은 환자들을 비교 분석 한다면 도움이 될 것이라고 판단된다. 또한 퇴원선량과 병실의 오염도에 영향을 줄 수 있는 기타 다른 요인들에 대해서도 지속적으로 연구한다면 환자 본인의 피폭뿐만 아니라 가족과 그주변인 의료진들에게도 조금이나마 피폭의 영향을 감소 시킬 수 있을 것이라고 사료된다.

  • PDF

방사성요오드(I-131) 격리병실 치료 관리를 위한 환자의 체외방사선량률과 상주 보호자의 피폭선량평가 (Evaluation of Caregivers' Exposed Dose and Patients' External Dose Rate for Radioactive Iodine (I-131) Therapy Administration in Isolated Ward)

  • 강석진;이두현;소영;이정우
    • 대한방사선기술학회지:방사선기술과학
    • /
    • 제45권4호
    • /
    • pp.347-353
    • /
    • 2022
  • In this study, the radiation dose rate was measured by time and distance and evaluated whether radiation dose rate was suitable for domestic and international discharge criteria. In addition, the radiation dose emitted from the patient was measured with a glass dosimeter to evaluate the exposure dose if the caregiver stays in the isolated ward by placing a humanoid phantom instead of the caregiver at a distance of 1 m from the patient, on the second day of treatment. After 23 hours of isolation, the radiation dose rates at a distance of 1 m were 20.54 ± 6.21 µSv/h at 2.96 GBq administration and 27.94 ± 12.33 µSv/h at 3.70 GBq administration. The radiation dose rates at a distance of 1 m were 25.90 ± 2.21 µSv/h when 2.96 GBq was administered and 34.22 ± 10.06 µSv/h when 3.70 GBq was administered after 18 hours of isolation. However, if the isolation period is short may cause unnecessary radiation exposure to the third person. The reading of the attached dosimeter from the morning of the second day of treatment until removal was 0.01 to 0.95 mSv, which is a surface dose determined by the International Commission on Radiation Units and Measurements. And the depth dose was 0.01 to 0.99 mSv. On the second day of treatment, even if the patient caregivers stayed in the isolation ward, the exposure dose of the patient family did not exceed the effective dose limit of 5 mSv recommended by the ICRP and NCRP.