• Title/Summary/Keyword: Low and Intermediate-Level

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A Basical Study on the Preparing of Container Used for Treatment and Disposal of Low-and Intermediate-Level Radioactive Wastes(I) (저.중준위 방사성 폐기물의 고화처리 및 처분용 용기 개발을 위한 기초연구(1))

  • 홍원표;정수영;황의환;조헌영;김철규
    • Journal of the Korean Ceramic Society
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    • v.25 no.2
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    • pp.101-110
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    • 1988

  • In order to improve the physical properties of concrete used for treatment and disposal container of low-and intermediate-level radioactive wastes, OPC (ordinary portland cement), ACPC (asphalt coated portland cement) and EPC(epoxy-portland cement) concrete specimens were prepared, and the physical properties of each concrete specimen were tested. According to the experimental results, EPC concrete showed better physical properties than ACPC and OPC concrete, however, ACPC concrete proved to be a best material for treatment and disposal container of radwastes in view of economic aspect and physical properties.

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Environmental radiation monitoring program of low- and intermediate- level waste disposal site (중$\cdot$저준위 방사성폐기물 처분시설 환경방사선조사 계획)

  • 윤철환;한재문;김경덕
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.239-243
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    • 2003

  • Environmental monitoring program is investigated based on Atomic Energy Law and foreign country radiation monitoring programs on low-and intermediate level radioactive waste disposal site. It is anticipated that the number of radiation measurements and samples will be higher than those of NPP's. The radiation monitoring program on LLW disposal site should be well prepared reflecting PA, site characteristics and regulation.

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Glass Formulations for Vitrification of Low- and Intermediate-level Waste

  • Kim, Cheon-Woo;Park, Jong-Kil;Ha, Jong-Hyun;Song, Myung-Jae;Lee, Nel-Son;Kong, Peter-C.;Anderson, Gary-L.
    • Journal of the Korean Ceramic Society
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    • v.40 no.10
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    • pp.936-942
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    • 2003

  • In order to develop glass formulations for vitrifying Low-and Intermediate-Level radioactive Wastes (LILW) from nuclear power plants of Korea Hydro & Nuclear Power (KHNP) Co., Ltd., promising glass formulations were selected based on glass property model predictions for viscosity, electrical conductivity and leach resistance. Laboratory measurements were conducted to verify the model predictions. Based on the results, the models for electrical conductivity, US DOE 7-day Product Consistency Test (PCT) elemental release, and pH of PCT leachate are accurate for the LILW glass formulations. However, the model for viscosity was able to provide only qualitative results. A leachate conductivity test was conducted on several samples to estimate glass leach resistance. Test results from the leachate conductivity test were useful for comparison before PCT elemental release results were available. A glass formulation K11A meets all the KHNP glass property constraints, and use of this glass formulation on the pilot scale is recommended. Glass formulations K12A, K12B, and K12E meet nearly all of the processing constraints and may be suitable for additional testing. Based on the comparison between the measured and predicted glass properties, existing glass property models may be used to assist with the LILW glass formulation development.

  • https://doi.org/10.4191/KCERS.2003.40.10.936 인용 PDF KSCI

Preparation and Management of the Input Data for the Safety Assessment of Low- and Intermediate-level Radioactive Waste Disposal Facility in Korea (중·저준위 방사성폐기물 처분시설 안전성평가를 위한 입력데이터 설정 및 관리에 대한 고찰)

  • Park, Jin Beak;Kim, Hyun-Joo;Lee, Dong-Hee
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.12 no.4
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    • pp.345-361
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    • 2014

  • The systematic quality assurance activities on documents of the safety assessment are required for the safety case of the low- and intermediate-level radioactive waste disposal facility. In this paper, quality assurance system focused on the input data including the site characterization, groundwater flow, system design and monitoring are prepared and discussed. Rule for the input data selection is suggested and applied for the safety assessment which is based on the in-situ/experiment observations, final facility design and waste pileup plan, engineered barrier, field monitoring, recent biosphere, and radionuclide inventory. The reduction of data uncertainty will be expected to contribute to the safety of disposal facility further.

  • https://doi.org/10.7733/jnfcwt.2014.12.4.345 인용 PDF KSCI KPUBS HTML

Development of the Safety Case Program for the Wolsong Low- and Intermediate-Level Radioactive Waste Disposal Facility in Korea (중·저준위 방사성폐기물 처분시설을 위한 Safety Case 종합프로그램의 개발)

  • Park, Jin Beak;Jeong, Jong Tae;Park, Joo-Wan
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.12 no.4
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    • pp.335-344
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    • 2014

  • The safety case program has been prepared for the development of the disposal facility of low- and intermediate-level radioactive waste in Korea. For the development of the radioactive waste disposal facility, this program can be applied for the safety demonstration of the facility and for the safety judgment of development step based on the international standards and domestic development environment. Systematic safety approach of this program includes the safety strategies such as optimization, robustness, demonstrability and defense-in-depth principle which are based on the safety principle and objectives. From the quality of assessment basis, safety arguments focused on the uncertainty management and the confidence building can assure the disposal safety during the step-wise safety assessment.

  • https://doi.org/10.7733/jnfcwt.2014.12.4.335 인용 PDF KSCI KPUBS HTML