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      KCI등재 SCIE SCOPUS

      Radiological safety analysis of a newly designed spent resin mixture treatment facility during normal and abnormal operational scenarios for the safety of radiation workers

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      https://www.riss.kr/link?id=A108593979

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      다국어 초록 (Multilingual Abstract)

      The radiological safety of workers in a newly developed microwave-based spent resin treatment facility was assessed based on work location and operational scenarios. The results show that the remoteoperation room worker was exposed to maximum annual dose of 3.19Eþ00 mSv, which is 15.9% of the dose limit, thereby confirming radiological safety. Inside the pathway, annual doses in the range of 7.87E-02e2.07E-01 mSv were measured initially at the mock-up tank and later at the point between the spent resin separation and treatment parts. The dose of emergency maintenance workers was below the dose limit (4.08E-03e4.99Eþ00 mSv); however, before treatment (separation and microwave), the dose of maintenance and repair workers exceeded the dose limit. The doses of the effluent removal workers at the zeolite and activated carbon storage tank and spent resin storage tank were the lowest at 2.79E-01 e2.87E-01 mSv and 9.27E-01 mSv in “1 h” and “4e5 h of operation”, respectively. The immediately lower and upper layers of the facility room exhibited the highest annual doses of 1.84Eþ00 and 3.22Eþ00 mSv, respectively. Through this study, a scenario that can minimize the dose considering the movement of spent resin through the facility can be developed
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      The radiological safety of workers in a newly developed microwave-based spent resin treatment facility was assessed based on work location and operational scenarios. The results show that the remoteoperation room worker was exposed to maximum annual d...

      The radiological safety of workers in a newly developed microwave-based spent resin treatment facility was assessed based on work location and operational scenarios. The results show that the remoteoperation room worker was exposed to maximum annual dose of 3.19Eþ00 mSv, which is 15.9% of the dose limit, thereby confirming radiological safety. Inside the pathway, annual doses in the range of 7.87E-02e2.07E-01 mSv were measured initially at the mock-up tank and later at the point between the spent resin separation and treatment parts. The dose of emergency maintenance workers was below the dose limit (4.08E-03e4.99Eþ00 mSv); however, before treatment (separation and microwave), the dose of maintenance and repair workers exceeded the dose limit. The doses of the effluent removal workers at the zeolite and activated carbon storage tank and spent resin storage tank were the lowest at 2.79E-01 e2.87E-01 mSv and 9.27E-01 mSv in “1 h” and “4e5 h of operation”, respectively. The immediately lower and upper layers of the facility room exhibited the highest annual doses of 1.84Eþ00 and 3.22Eþ00 mSv, respectively. Through this study, a scenario that can minimize the dose considering the movement of spent resin through the facility can be developed

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      참고문헌 (Reference)

      1 Z. Wan, "Treatment of spent radioactive anionic exchange resins using Fenton-like oxidation process" 284 : 733-740, 2016

      2 K. Kim, "Treatment of ion exchange resins used in nuclear power plants by super-and sub-critical water oxidationeA road to commercial plant from bench-scale facility" 189 : 213-221, 2012

      3 J. Wang, "Treatment and disposal of spent radioactive ion-exchange resins produced in the nuclear industry" 78 : 47-55, 2015

      4 A. Hussain, "Treatment and conditioning of spent ion exchange resin from nuclear power plant" 15 : 79-89, 2013

      5 T.B. Tahir, "Radioactive waste management: policy & strategy of Pakistan" 2007

      6 A.C. Nilsson, "On the Swelling of Ion Exchange Resins Used in Swedish Nuclear Power Plants" Swedish Nuclear Power Inspectorate 1988

      7 International Atomic Energy Agency, "Management of spent ionexchange resins from nuclear power plants" 1981

      8 I. Plecas, "Influence of natural sorbents on the immobilization of spent ion exchange resins in cement" 269 : 181-185, 2006

      9 Y. P. Korchagin, "Improvement of technology for treatment of spent radioactive ion-exchange resins at nuclear power stations" 57 : 593-597, 2010

      10 N. H. Hamodi, "Immobilization of spent ion exchange resin arising from nuclear power plants : an introduction" 3 : 7-18, 2009

      1 Z. Wan, "Treatment of spent radioactive anionic exchange resins using Fenton-like oxidation process" 284 : 733-740, 2016

      2 K. Kim, "Treatment of ion exchange resins used in nuclear power plants by super-and sub-critical water oxidationeA road to commercial plant from bench-scale facility" 189 : 213-221, 2012

      3 J. Wang, "Treatment and disposal of spent radioactive ion-exchange resins produced in the nuclear industry" 78 : 47-55, 2015

      4 A. Hussain, "Treatment and conditioning of spent ion exchange resin from nuclear power plant" 15 : 79-89, 2013

      5 T.B. Tahir, "Radioactive waste management: policy & strategy of Pakistan" 2007

      6 A.C. Nilsson, "On the Swelling of Ion Exchange Resins Used in Swedish Nuclear Power Plants" Swedish Nuclear Power Inspectorate 1988

      7 International Atomic Energy Agency, "Management of spent ionexchange resins from nuclear power plants" 1981

      8 I. Plecas, "Influence of natural sorbents on the immobilization of spent ion exchange resins in cement" 269 : 181-185, 2006

      9 Y. P. Korchagin, "Improvement of technology for treatment of spent radioactive ion-exchange resins at nuclear power stations" 57 : 593-597, 2010

      10 N. H. Hamodi, "Immobilization of spent ion exchange resin arising from nuclear power plants : an introduction" 3 : 7-18, 2009

      11 M. A. Hafeez, "Fenton-like treatment for reduction of simulated carbon-14 spent resin" 9 : 104740-, 2021

      12 L. Wang, "Experimental investigation on gasification of cationic ion exchange resin used in nuclear power plants by supercritical water" 126437 : 2021

      13 변재훈 ; 최우년 ; 김희령, "Dose evaluation of workers according to operating time and outfl ow rate in a spent resin treatment facility" 한국원자력학회 53 (53): 3824-3836, 2021

      14 F. Vermeersch, "Development of the VISIPLAN ALARA Planning Tool" 1998

      15 G. I. Park, "Development of Adsorbent for C-14 Gas Trapping and Characteristics Evaluation" 2006

      16 M. S. Palamarchuk, "Decontamination of spent ion-exchange resins contaminated with cesium radionuclides" 465 : 308-312, 2015

      17 W. Feng, "Decomposition of spent radioactive ionexchange resin using photo-Fenton process" 95 : 2522-2529, 2020

      18 J. Li, "Advances in cement solidification technology for waste radioactive ion exchange resins : a review" 135 : 443-448, 2006

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