• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.447-452
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• 1998

우리나라에서도 고준위폐기물 처분시설의 장기안전성 확보를 위한 기초연구가 시작되고 있어 안전성 기준에 대한 논의가 필요한 시점이다. 여기서는 고준위폐기물 처분시설의 안전성 기준에 대한 국제기관들의 권고하는 기준들을 조사하고, 현재 여러 나라에서 제안되거나 개정중에 있는 기준들을 비교 분석하였다. 안전성기준에서의 큰 차이점은 유도기준의 필요성(현재 미국만의 유도기준을 사용), ALARA 적용문제, 종합적 위험도 적용방법론의 문제, 위험도 수준등에서 나타나고 있으며, 특히 미래 상황의 불확실성 때문에 현재 및 개 국가에서 제시하고 있는 안전성평가기간 (10,000면)은 계속 논란이 일 것으로 보인다. 미래 예측이 어느 정도 가능한 최소한의 기간(수천년 혹은 만년)까지는 위험도를 기준으로, 그리고 그 이후는 지표로의 누출율을 기준으로 정하는 것도 바람직한 대안이 될 것으로 생각된다. 또한 안전성기준은 설계자로 하여금 대안분석을 통한 최적화를 방해하는 구체적인 유포기준보다는 융통성을 어느 정도 부여하는 방향으로 설정되는 것이 바람직한 것으로 사료된다.

• The Korean Journal of Archival Studies
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• no.67
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• pp.139-203
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• 2021

The study aims to analyze the records management reference tables currently being utilized and to provide directions on how should be redesigned in the future to operate as a appraisal tool for national archives. From the perspective of "what records should be the national archives", it was intended to analyze the records management reference tables, particularly in the environmental public authorities, and to propose future improvements. The main focus of the analysis is on appraising records that need to be preserved as national archives, and therefore, prior to analysis of the tables, it examines whether the archival selection criteria are clearly presented. Subsequently, the study is conducted how to implement this criteria through the records management reference table of each agency and how its implementation system will be constructed. The analysis will be focused on Ministry of Environment's records management reference table and records schedules or appraisal/selection tools of the central and federal institutions that perform environmental functions in U.S., Australia, and UK.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.219-221
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• 2004

국가의 규제기관과 처분장에서는 방사성 폐기물의 안전한 영구처분을 위하여 폐기물 수용(인수)기준을 폐기물 발생자에게 준수토록 요구하게 되는데 이러한 폐기물 수용(인수)기준은 처분시설의 가동동안 인간과 환경 보호 그리고 최대 300년간의 제도적 통제기간을 고려하여 처분장의 안전성 확보를 위하여 설정되어진다. 폐기물 수용(인수)기준중 고화체의 안정성 평가와 관련하여 미국(NRC/BTP)은 폐기물의 종류와 고화매질에 따라 유리수, 압축강도, 방사성 조사특성, 미생물 영향 특성, 침수 및 침출 특성, 열순환 특성 등에 대하여 표준시험법을 제시하였으며, 또한 그의 기술기준치도 제시하고 있다. 그리고 프랑스(DRDD/ BECC)에서는 미국보다 매우 세밀하게 평가항목들을 분류하는 등의 처분장 운영국가에서는 고화체의 안정성관련 평가시험들을 처분 환경과 처분방식에 맞게 표준화하고 있다. 한편 국내에서는 과기부 고시 제2001-32호 "중.저준위 방사성폐기물 인도규정"이 있으나 이에는 고화체 관련하여 정성적인 안정성에 대하여서만 기술되어 있다. 이에 따라 원전폐기물 고화체에 대한 안정성 평가를 위한 시험법을 선정하기 위하여 아래 그림과 같은 절차에 따라 수행토록 하였다. 우선 대표적인 천층처분 운영국가인 미국과 프랑스의 시험법 그리고 IAEA 권고 시험법과 유사관련 한국 산업표준법들을 조사하고, 이들 시험법들의 주요 차이점을 기술적 관점에서 비교평가하고, 이어서 모의 방사성 및 비방사성 고화체를 이용하여 상기 시험법들을 각각 적용하고 또한 이들 시험법들간의 차이(시험 조건, 시편의 크기 등)에 기인한 상호 비교시험을 통하여 얻어진 시험결과들을 종합적으로 비교 검토하여 보수적 관점에서 시험법을 선정하는 것으로 방향을 잡았다. 이때 시험결과를 얻기 위한 모든 과정에 품질보증 활동을 적용키로 하였으며, 시험결과 분석/평가 과정과 시험법 선정에 각계(규제기관, 학계, 발전소 현장 및 산업계 등) 전문가로부터 기술자문회의를 통하여 자문 의견을 받기로 하였다. 특히 현재 폐기물 인수 기술기준치가 설정된 국가의 시험법을 심층 있게 검토하기로 하였다.검토하기로 하였다.

• 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.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.11a
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• pp.126-133
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• 2005

Securing of radioactive waste disposal site and the related operations for disposal of low and intermediate level radioactive waste is being actively carried out in Korea. For disposal of radioactive wastes, physicochemical and radiological status and integrity of radioactive wastes must be secured first. Also, waste generators must provide this information to disposers. In addition, to secure the safety of waste disposal, waste acceptance criteria (WAC) and site specific waste acceptance criteria (SWAC) to consider characteristics of the disposal site are required. Radioactive wastes must be processed, generated, managed and transferred in accordance with these criteria. [1] For this, evaluation of properties on each of the radioactive wastes must be performed. However, in reality, atomic power plants are experiencing difficulties in relation to this due to the large quantity of radioactive waste generation. In order to solve this problem, IAEA and major overseas countries have developed, thus are using waste certification program (WCP) and quality assurance program (QAP) [2,3]. On the basis of these programs, radioactive waste certification program has been developed for safe disposal of radioactive wastes in Korea to satisfy the provisions specified in 'low and intermediate level radioactive waste transfer guidelines' of announcement No. 2005-18 from the Ministry of Science and Technology and specific site waste acceptance criteria (tentative plan). In addition, it is being planned to administer amendment on commercial atomic power plant related procedures and ensile staff training in order for early introduction and operation of radioactive waste certification system.

• 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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• 2006.11a
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• pp.327-328
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• 2006

중 저준위방사성폐기물(이하, '방폐물'이라 함)을 처분시설로 안전하고 효율적으로 운반하기 위하여 원자력법[1][2] 및 IAEA 안전운반규정(3) 등 국내외 관련규정의 기술기준을 만족시키는 안전성이 확보된 운반용기를 사용하여야 한다. 방폐물이 저준위비방사능(LSA: Low Specific Activity)물질 또는 표면오염물체(SCO; Surface Contaminated Object)로 분류되고 전용상태로 운반되는 경우는 거의 IP-2형 운반용기를 이용하여 운반하는 것이 가능하다. 방폐물 처분시설이 경주의 임해지역에 건설되어 운영된 것이므로 일부를 제외한 대부분의 방폐물은 IP-2형 운반용기에 적재하여 전용선박을 이용하여 해상으로 운반하게 된다. 전용선박은 크레인을 이용하여 화물을 선적하고 하역하는 Lo/Lo(Lift-on/Lift-off) 방식으로 IMO 규정 및 국내 선박법에 따라 국내에서 설계, 건조될 예정이며, 선박의 규모는 총 톤수 약 2,000톤이며, 약 1,600드럼의 방폐물을 적재할 수 있다. 여기서는 방폐물의 해상운반을 위한 IP-2형 운반용기에 대한 요건 및 관련규정에 따른 기술기준을 입증하기 위한 건전성 평가방안에 대하여 기술하였다.

• Journal of Korean Society of Archives and Records Management
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• v.20 no.1
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• pp.47-67
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• 2020

Unless the records appraisal system is properly overhauled, there is no future for public records management. This study aims to highlight challenging issues and present improvement tasks necessary for the readjustment of the public records appraisal system at the national level. First, public records appraisal policies are divided into five categories: i) statements on appraisal policy and selection criteria, ii) appraisal tools such as disposition authorities, iii) subject of appraising, iv) appraisal procedures, and v) responsibility and authority in appraisal and disposition process. Second, the domestic situation is identified for each category. Third, policies of the United States, United Kingdom, Australia, and Canada are compared, and implications are derived for each category. Fourth and last, the tasks for the readjustment of the public appraisal system are proposed based on these analyses.

• The Korean Journal of Nuclear Medicine Technology
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• v.26 no.1
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• pp.15-26
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• 2022

Purpose Recently, in the process of examining the self-disposal of radioactive waste by the Korea Institute of Nuclear Safety, it is difficult to reach the final approval process for self-disposal. In connection with this, we intend to increase the processing efficiency of self-disposal and strengthen safety by analyzing cases of recent supplementary matters. Materials and Methods From 2018 to 2021, we compare and review a supplementary requests that preparing the procedures and plans for the self-disposal of radioactive waste by 20 institutions. In this regard, based on the provisions of the Atomic Energy Safety Act, we derive a detailed proposals for the self-disposal of radioactive waste by arranging the review processing period calculation and supplementary requests that occurred during the review process. Results The representative supplementary requests of the Korea Institute of Nuclear Safety are the calculation of the storage period by type and nuclide of radioactive waste, the contents of the packaging container, the RASIS reporting method, the planned storage method for self-disposal, confirmation of the final disposal company, and the storage period of the waste filter Calculation, radioactive labeling, etc. And it is emphasized as important. Conclusion The expected effects of the guidelines reflecting the latest supplements include reduction of the time required for document preparation and increase of work processing efficiency, improvement of storage efficiency in the radioactive waste storage room, and economic cost reduction. If the radioactive waste self-disposal guideline presented in this study is applied to the field, it is thought that it will be helpful in improving the work efficiency of those who are experiencing difficulties.

• Economic and Environmental Geology
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• v.51 no.2
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• pp.167-176
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• 2018

It is necessary to consider various geological parameters such as lithology, geological structure, earthquake, hydraulic geology, geochemistry, geological engineering, and geothermal in order to select potential sites for HLW(high-level radioactive waste) geological disposal. In particular, the geological lineament reflects the characteristics of various geological parameters and can be used as an important criterion for site selecting such as nuclear power plants and HLW repositories. In this paper, the Finnish lineament classification method for HLW disposal site selection through the lineament analysis was applied to the lineament data in the Korean peninsula. For this purpose, we used previous lineament data from the KIGAM(Korea Institute of Geoscience and Mineral Resources) and obtained new lineament data from the field geologists such as structural geologist, paleoseismologist, and geomorphologist. To ensure the reliability of the new lineament analysis data, we used high-resolution satellite images and hill-shade relief maps which were constructed by a digital elevation model. In the prevailing direction analysis from the acquired lineament data, the NNE-SSW direction was the most dominant, but the ENE-WSW and NNW-SSE directions also showed highly frequency depending on the experts. Applying the Finnish classification method, the geometrical development characteristics of the lineament corresponding to the Class 1 and 2 used for the wide-wide candidate site were compared. As a result of direction analysis for Class 1, the NNE-SSW direction was the most dominant and the WNW-ESE direction also showed a high frequency. In the case of Class 2, the NNE-SSW is the most prevalent and WNW-ESE or ENE-WSW direction also had highly frequency depending on the experts. Different lineament analysis results based on the same data are interpreted as a result of subjective experience and analytical criteria from the every experts. Therefore, it is necessary to establish integrated criteria and consider geophysical data for the publication of reliable nation-wide lineament map.