• Nuclear industry
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• v.17 no.2 s.168
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• pp.62-69
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• 1997

원자력발전소에서 발생되는 방사성 폐기물을 안정된 폐기물로 만들어 환경 문제를 극소화시키고, 또한 폐기물의 부피를 혁신적으로 감소시켜 처분비를 줄일 수 있는 방법 중 현재 가장 적합한 방법으로 시행되고 있는 기술은 폐기물의 유리 고화 기술일 것이다. 고준위 폐기물의 유리 고화 기술은 이미 상용화되고 있고, 중$\cdot$건설 단계에 와있다. 우리 나라의 경우 현재 방사성 폐기물 처분장 확보에 큰 어려움을 겪고 있는데, 이 기술이 성공하면 중$\cdot$저준위 방사성 폐기물의 처분 문제가 크게 줄어들 것이다. 방사성 폐기물의 유리 고화 기술의 개발 이용 현황과 앞으로의 과제 등을 알아본다.

• The Korean Journal of Nuclear Medicine Technology
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• v.21 no.2
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• pp.13-27
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• 2017

Purpose In the procedure of domestic medical radioactive self-disposal, there are many requests of supplementation and difficulties on the screening process. In this regard, presentation of basic guideline will improve the work processing efficiency of medical institution radioactive waste. From 2015 to 2016, We reviewed and compared a supplementary requests of domestic fifteen medical institution radioactive self-disposal Plan & Procedure manual. In connection with this, we derive the details of the radioactive waste document based on the relative regulation of nuclear safety Act. The representative supplementary requests of Korea Institute of Nuclear Safety are disposal method of non-flammability radioactive waste, storage method of scheduled self-disposal waste, the legitimacy of self-disposal and pre-treatment of self-disposal, reference radioactivity of disused filter and output of storage period, attachment the evidential matter of measurement efficiency when using a gamma counter. Through establishing a medical radioactive waste guideline, we can clearly suggest a classification standard of radioactive nuclide and the type of occurrence. As a result, we can confirm the reduction of examination processing period while preparing a self-disposal document and there is no spending expenses for business agency. Also, the storage efficiency of facility will better and reduce the economic expenses. On the basis of this guideline, we will expect a contribution to the improvement of work efficiency for officials who has a working-level difficulty of radioactive waste self-disposal.

• Nuclear Engineering and Technology
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• v.26 no.4
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• pp.578-599
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• 1994

방사성 폐기물 처분장의 건설에 가장 중요한 부분중의 하나는 처분안전성의 확보일 것이다. 처분장 안전성평가는 처분장이 입지하는 환경에 대한 실험실적 자료 또는 현장 자료의 충분한 데이타베이스와 처분시스템에서 일어날 수 있는 주요한 프로세스를 기술하는 수학적 모델을 통하여 이루어지게 된다. 처분시스템의 기본적인 기능은 처분된 폐기물고화체를 인간환경으로 부터 완벽하게 고립시켜 처분장내에 영구적으로 격리시키는 것이다. 그렇지만 정상적이든 비정상적이든 핵종은 항상 유출될 가능성이 있고 설사 이러한 경우라도 충분히 안전한 것을 입증하는 것이 처분장 성능 평가와 안전성평가의 주요한 목적이 된다. 한편 장기간에 걸친 처분 안전성 평가는 전산 프로그램을 통한 이론적 예측에 의해서만 가능하므로, 처분안전성 평가도구의 개발 및 확보의 중요성은 매우 크다고 할 수 있다. 이 연구에서는 처분장이 입지하는 암반 매질에서의 핵종의 이동을 기술할 수 있는 여러 모델을 검토하고, 특정 처분부지에 대한 종합적 안전성 평가를 수행할 수 있는 방법론을 제시할 목적으로 임의의 1개 부지의 지형도및 추정가능한 지질관련 자료를 이용하여 해당 부지에 대한 가상의 핵종 유출 시나리오를 설정하여 부지특성적인 예비 종합 안전성 평가를 수행하여 보았다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.270-275
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• 2003

The heat transfer analysis was conducted for the conceptual design of high level waste canisters. The temperature distribution due to the heat generation from four PWR spent fuel bundles which were contained in a canister located in a borehole 500 m below the surface was obtained. NISA computer program based upon FEM was used for the numerical solution. The temperature distribution in the composite system of $\ulcorner$canister ＋ buffer ＋ tunnel ＋ rock$\lrcorner$ due to heat generation from the spent fuel was obtained. In the case of 40m tunnel spacing and 6m borehole spacing the temperature showed the maximum value of $87.5^{\circ}C$around 15-16 years after disposal and decreased.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.1
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• pp.55-62
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• 2012

As an alternative of the high-level radioactive waste disposal in the subsurface repository, a deep borehole disposal is reviewed by several nuclear advanced countries. In this study, the state of the art on the borehole disposal researches was reviewed, and the possibility of borehole disposal in Korean peninsula was discussed. In the deep borehole disposal concept radioactive waste is disposed at the section of 3 - 5km depth in a deep borehole, and it has known that it has advantages in performance and cost due to the layered structure of deep groundwater and small surface disposal facility. The results show that it is necessary to acquisite data on deep geologic conditions of Korean peninsula, and to research the engineering barrier system, numerical modeling tools and disposal techniques for deep borehole disposal.

• Journal of Energy Engineering
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• v.29 no.1
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• pp.63-74
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• 2020

The Kori-Unit 1 nuclear power plant, which is scheduled for decommissioning after permanent shutdown, is expected to generate a large amount of various types of radioactive waste during decommissioning process. For concrete radioactive waste, which is expected to occupy the most amount, it is important to analyze the current waste disposal status and legal limitations and to prepare an appropriate and efficient disposal method. Concrete radioactive waste is waste of various levels, of which the clearance level is bioshield concrete. In this paper, clearance radioactive waste safety evaluation was performed using the RESRAD code, which is a safety evaluation code, based on the activation evaluation results for the wastes with the clearance level. The clearance scenario of the target radioactive waste was selected and the individual's exposure dose was calculated at the time of clearance to determine whether the clearance criteria limit prescribed by the Nuclear Safety Act was satisfied. As a result of the evaluation, the results showed significantly lower results and satisfied the criteria value. Based on the results of this clearance safety assessment, the appropriate disposal method for bioshield concrete, which are the clearance wastes of subject of deregulation, was suggested.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.18 no.2_spc
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• pp.291-303
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• 2020

The Kori-Unit 1 nuclear power plant, which is scheduled to be decommissioned after permanent shutdown, is expected to generate large amounts of various types of radioactive waste during the decommissioning process. Among these, nuclear reactors and internal structures have high levels of radioactivity and the dismantled structure must have the proper size and weight on the primary side. During decommissioning, it is important to prepare an appropriate and efficient disposal method through analysis of the disposal status and the legal restrictions on wastes generated from the reactors and internal structures. Nuclear reactors and internal structures generate radioactive wastes of various levels, such as medium, very low, and clearance. A radiation evaluation indicates that wastes in the clearance level are generated in the reactor head and upper head insulation. In this study, a clearance waste safety evaluation was conducted using the RESRAD-RECYCLE code, which is a safety evaluation code, based on the activation evaluation results for the clearance level wastes. The clearance scenario for the target radioactive waste was selected and the maximum individual and collective exposure doses at the time of clearance were calculated to determine whether the clearance criteria limit prescribed by the Nuclear Safety Act was satisfied. The evaluation results indicated that the doses were significantly low, and the clearance criteria were satisfied. Based on the safety assessment results, an appropriate metal recycle and disposal method were suggested for clearance, which are the subject of the deregulation of internal structures of nuclear power plant.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2008.11a
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• pp.245-246
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• 2008

한국원자력연구원은 1997년부터 10여년 동안 정부 출연 연구기관으로서 원자력 발전의 부산물인 사용후핵연료를 포함한 다양한 방사성폐기물의 안전한 처분을 확인하기 위한 연구 개발에 주력해 왔다. 처분 안전성 확인(Safety Case)이란 개념은 지난 10여년 전부터 OECD/NEA와 SKB 등 서구 지역 국가들을 중심으로 발전된 처분 안전성에 대한 인허가 및 신뢰성 증진을 위한 통합적 접근 방안으로 미국, 영국 등 법률적 규정에 의거 안전성을 규제 기관과 법원 등이 개업된 청문회 등을 통해 다루는 체제와 상반되는 개념이다. 이러한 처분 안전성 확인은 처분 개념과 안전성 확인 개념화부터 인허가에 관련된 각종 보고서 작성과 이해성 증진을 위한 다양한 활동을 총합하는 개념으로 방사성폐기물 사업자가 아닌 객관적이고 전문성 있는 기관들이 추진하는 것이 바람직 할 것이다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2015.10a
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• pp.413-414
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• 2015

국내 최초로 가연성 해체폐기물 부피감용을 위해 안전하게 시설을 운영하고 있어 소각에 대한 국민인식 재고에 기여할 수 있으며, 우라늄변환시설의 가연성 해체 폐기물 소각을 통해 U 핵종오염 폐기물 소각기술을 확보하여 원자력시설 운영 효율향상, 처분비용 절감 뿐만 아니라 유해물질의 무해화로 최종처분장의 안전성 관리 최적화에 기여하고, 향후 원자력시설의 해체 및 해체 폐기물 처리/처분사업에 기술을 적극 활용할 예정이다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.05a
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• pp.183-184
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• 2016