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      KCI등재 SCIE SCOPUS

      Validation of a New Design of Tellurium Dioxide-Irradiated Target

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      https://www.riss.kr/link?id=A103669908

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      다국어 초록 (Multilingual Abstract)

      Production of iodine-131 by neutron activation of tellurium in tellurium dioxide (TeO2) material requires a target that meets the safety requirements. In a radiopharmaceutical production unit, a new lid for a can was designed, which permits tight sealing of the target by using tungsten inert gas welding. The leakage rate of all prepared targets was assessed using a helium mass spectrometer. The accepted leakage rate is ≤ 10−4 mbr.L/s, according to the approved safety report related to iodine-131 production in the TRIGA Mark II research reactor (TRIGA: Training, Research, Isotopes, General Atomics). To confirm the resistance of the new design to the irradiation conditions in the TRIGA Mark II research reactor's central thimble, a study of heat effect on the sealed targets for 7 hours in an oven was conducted and the leakage rates were evaluated. The results show that the tightness of the targets is ensured up to 600°C with the appearance of deformations on lids beyond 450°C. The study of heat transfer through the target was conducted by adopting a one-dimensional approximation, under consideration of the three transfer modes—convection, conduction, and radiation. The quantities of heat generated by gamma and neutron heating were calculated by a validated computational model for the neutronic simulation of the TRIGA Mark II research reactor using the Monte Carlo N-Particle transport code. Using the heat transfer equations according to the three modes of heat transfer, the thermal study of I-131 production by irradiation of the target in the central thimble showed that the temperatures of materials do not exceed the corresponding melting points. To validate this new design, several targets have been irradiated in the central thimble according to a preplanned irradiation program, going from 4 hours of irradiation at a power level of 0.5 MW up to 35 hours (7 h/d for 5 days a week) at 1.5 MW. The results show that the irradiated targets are tight because no iodine-131 was released in the atmosphere of the reactor building and in the reactor cooling water of the primary circuit.
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      Production of iodine-131 by neutron activation of tellurium in tellurium dioxide (TeO2) material requires a target that meets the safety requirements. In a radiopharmaceutical production unit, a new lid for a can was designed, which permits tight seal...

      Production of iodine-131 by neutron activation of tellurium in tellurium dioxide (TeO2) material requires a target that meets the safety requirements. In a radiopharmaceutical production unit, a new lid for a can was designed, which permits tight sealing of the target by using tungsten inert gas welding. The leakage rate of all prepared targets was assessed using a helium mass spectrometer. The accepted leakage rate is ≤ 10−4 mbr.L/s, according to the approved safety report related to iodine-131 production in the TRIGA Mark II research reactor (TRIGA: Training, Research, Isotopes, General Atomics). To confirm the resistance of the new design to the irradiation conditions in the TRIGA Mark II research reactor's central thimble, a study of heat effect on the sealed targets for 7 hours in an oven was conducted and the leakage rates were evaluated. The results show that the tightness of the targets is ensured up to 600°C with the appearance of deformations on lids beyond 450°C. The study of heat transfer through the target was conducted by adopting a one-dimensional approximation, under consideration of the three transfer modes—convection, conduction, and radiation. The quantities of heat generated by gamma and neutron heating were calculated by a validated computational model for the neutronic simulation of the TRIGA Mark II research reactor using the Monte Carlo N-Particle transport code. Using the heat transfer equations according to the three modes of heat transfer, the thermal study of I-131 production by irradiation of the target in the central thimble showed that the temperatures of materials do not exceed the corresponding melting points. To validate this new design, several targets have been irradiated in the central thimble according to a preplanned irradiation program, going from 4 hours of irradiation at a power level of 0.5 MW up to 35 hours (7 h/d for 5 days a week) at 1.5 MW. The results show that the irradiated targets are tight because no iodine-131 was released in the atmosphere of the reactor building and in the reactor cooling water of the primary circuit.

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      참고문헌 (Reference)

      1 Centre d’Etude de l’Energie Nucleaire, "groupe d'exploitation du reacteur BR2 et des installations connexes JMB/JMG/RH, BR2doigt de gant DG 36/01, Rapport de l'incident survenu le 23fevrier" 1971

      2 International Atomic Energy Agency, "Training Guidelines in Non-destructive Testing Techniques: Leak Testing at Level 2"

      3 Thermo Fisher Scientific, "Software Manual, Iodine Monitor FHT 1702 L, Thermo Electron (Erlangen) GmbH"

      4 B. El Bakkari, "Safety Analysis Report of CENM 2 MW TRIGA Mark-II research reactor" 2012

      5 M. Khalid, "Reuse of decayed tellurium dioxide target for production of iodine-131" 299 : 591-694, 2014

      6 International Standard ISO 9978, "Radiation Protection, Sealed Radioactive Sources, Leakage Test Methods"

      7 M.S. Islam, "Operation experience with the 3 MW TRIGA Mark-II research reactor of Bangladesh" 2004

      8 Isotope Technologie Dresden, "Operating Document, Process Description for Iodine 131, ITD-GmbH, 22.007"

      9 International Atomic Energy Agency, "Manual for Reactor Produced Radioisotopes, IAEA-TECDOC-1340"

      1 Centre d’Etude de l’Energie Nucleaire, "groupe d'exploitation du reacteur BR2 et des installations connexes JMB/JMG/RH, BR2doigt de gant DG 36/01, Rapport de l'incident survenu le 23fevrier" 1971

      2 International Atomic Energy Agency, "Training Guidelines in Non-destructive Testing Techniques: Leak Testing at Level 2"

      3 Thermo Fisher Scientific, "Software Manual, Iodine Monitor FHT 1702 L, Thermo Electron (Erlangen) GmbH"

      4 B. El Bakkari, "Safety Analysis Report of CENM 2 MW TRIGA Mark-II research reactor" 2012

      5 M. Khalid, "Reuse of decayed tellurium dioxide target for production of iodine-131" 299 : 591-694, 2014

      6 International Standard ISO 9978, "Radiation Protection, Sealed Radioactive Sources, Leakage Test Methods"

      7 M.S. Islam, "Operation experience with the 3 MW TRIGA Mark-II research reactor of Bangladesh" 2004

      8 Isotope Technologie Dresden, "Operating Document, Process Description for Iodine 131, ITD-GmbH, 22.007"

      9 International Atomic Energy Agency, "Manual for Reactor Produced Radioisotopes, IAEA-TECDOC-1340"

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      학술지 이력

      학술지 이력
      연월일 이력구분 이력상세 등재구분
      2023 평가예정 해외DB학술지평가 신청대상 (해외등재 학술지 평가)
      2020-01-01 평가 등재학술지 유지 (해외등재 학술지 평가) KCI등재
      2014-01-01 평가 SCIE 등재 (등재유지) KCI등재
      2014-01-01 평가 SCOPUS 등재 (등재유지) KCI등재
      2011-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2009-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2007-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2006-07-31 학술지명변경 한글명 : Jorunal of the Korean Nuclear Society -> Nuclear Engineering and Technology
      외국어명 : 미등록 -> Nuclear Engineering and Technology
      KCI등재후보
      2004-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
      2003-01-01 평가 등재후보 1차 PASS (등재후보1차) KCI등재후보
      2002-01-01 평가 등재후보학술지 유지 (등재후보1차) KCI등재후보
      1999-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
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      학술지 인용정보

      학술지 인용정보
      기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
      2016 1.04 0.17 0.77
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.63 0.56 0.343 0.11
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