• 방사성폐기물학회지
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• 제20권2호
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• pp.193-207
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• 2022

Thermodynamically, TRUO_x, REO_x, and SrO_x can be chlorinated using ammonium chloride (NH₄Cl) as a chlorinating agent, whereas uranium oxides (U₃O₈ and UO₂) remain in the oxide form. In the preliminary experiments of this study, U₃O₈ and CeO₂ are reacted separately with NH₄Cl at 623 K in a sealed reactor. CeO₂ is highly reactive with NH₄Cl and becomes chlorinated into CeCl₃. The chlorination yield ranges from 96% to 100%. By contrast, U₃O₈ remains as UO₂ even after chlorination. We produced U/REO_x- and U/SrO_x-simulated fuels to understand the chlorination characteristics of the oxide compounds. Each simulated fuel is chlorinated with NH₄Cl, and the products are dissolved in LiCl-KCl salt to separate the oxide compounds from the chloride salt. The oxide compounds precipitate at the bottom. The precipitate and salt phases are sampled and analyzed via X-ray diffraction, scanning electron microscope-energy dispersive spectroscopy, and inductively coupled plasma-optical emission spectroscopy. The analysis results indicate that REO_x and SrO_x can be easily chlorinated from the simulated fuels; however, only a few of U oxide phases is chlorinated, particularly from the U/SrO_x-simulated fuels.

• 방사성폐기물학회지
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• 제19권1호
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• pp.51-58
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• 2021

Chemical decontamination of primary systems in a nuclear power plant (NPP) prior to commencing the main decommissioning activities is required to reduce radiation exposure during its process. The entire process is repeated until the desired decontamination factor is obtained. To achieve improved decontamination factors over a shorter time with fewer cycles, the appropriate flow characteristics are required. In addition, to prepare an operating procedure that is adaptable to various conditions and situations, the transient analysis results would be required for operator action and system impact assessment. In this study, the flow characteristics in the steady-state and transient conditions for the chemical decontamination operations of the Kori-1 NPP were analyzed and compared via the MARS-KS code simulation. Loss of residual heat removal (RHR) and steam generator tube rupture (SGTR) simulations were conducted for the postulated abnormal events. Loss of RHR results showed the reactor coolant system (RCS) temperature increase, which can damage the reactor coolant pump (RCP)s by its cavitation. The SGTR results indicated a void formation in the RCS interior by the decrease in pressurizer (PZR) pressure, which can cause surface exposure and tripping of the RCPs unless proper actions are taken before the required pressure limit is achieved.

• 방사성폐기물학회지
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• 제16권3호
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• pp.315-330
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• 2018

미임계 시설은 정상 또는 사고상태에서 핵임계안전성이 확보되어야 한다. 이를 위해선 계산된 임계도가 바이어스와 불확실도로 결정된 미임계상한치(USL)를 초과하지 않는다는 것을 검증하는 절차가 반드시 필요하다. 하지만 핵임계안전성 검증방법론은 여러 가지가 존재하며, 방법론이 달라지면 USL도 달라지므로 가장 적절한 한가지의 방법론으로 평가하는 것이 중요하다. 본 연구에서는 핵임계안전성 검증 방법론이 기술된 두 개의 문서를 비교 분석하여 한 가지 방법론으로 정립하였고, SCALE6.1 코드를 이용한 용기 설계에서의 미임계상한치 결정에 적용하였다.

• 방사성폐기물학회지
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• 제21권3호
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• pp.329-345
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• 2023

This paper described a method for analyzing the structural performance of a metal container used for disposing radioactive waste generated during the decommissioning of a nuclear power plant, and numerical analysis results of a method for reinforcing the container. The containers to be analyzed were those that can be used in near-surface and landfill disposal facilities scheduled to be operated at the Gyeongju radioactive waste disposal facility. Structural reinforcement of the container was performed by lattice reinforcement, column reinforcement, and bottom plate reinforcement. Accordingly, a total of 14 reinforcement cases were modeled. The external force causing damage to the container was set equivalent to the impact of a 9-m fall, accounting for the height of the vault at the near-surface disposal facility. The reinforcement methods with a high contribution to the structural performance of the container were concluded to be lattice and column reinforcements.

• 방사성폐기물학회지
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• 제18권spc호
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• pp.63-74
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• 2020

The operational safety assessment is an important part of a safety case for the deep geological repository of spent fuels. It consists of different stages such as the identification of initiating events, event tree analysis, fault tree analysis, and evaluation of exposure doses to the public and radiation workers. This study develops a probabilistic safety assessment method for the operational safety assessment and establishes an assessment framework. For the event and fault tree analyses, we propose the advanced information management system for probabilistic safety assessment (AIMS-PSA Manager). In addition, we propose the Radiological Safety Analysis Computer (RSAC) program to evaluate exposure doses to the public and radiation workers. Furthermore, we check the applicability of the assessment framework with respect to drop accidents of a spent fuel assembly arising out of crane failure, at the surface facility of the KRS⁺ (KAERI Reference disposal System for SNFs). The methods and tools established through this study can be used for the development of a safety case for the KRS⁺ system as well as for the design modification and the operational safety assessment of the KRS⁺ system.

• 방사성폐기물학회지
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• 제7권3호
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• pp.143-151
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• 2009

최근 미-북간 관계 개선 등으로 인하여 북핵 문제가 핵 검증단계로 진전될 것이라는 예상이 나오고 있다. 이제부터 우리 정부는 북핵 프로그램의 성공적 검증 폐기를 위해, 북한의 신고 후 전개될 상황에 대비하여 철저히 준비해야 한다. 본 논문에서는 구 소련과 이라크의 대량살상무기 검증 폐기 사례로부터 두 나라의 대량살상무기 검증 폐기 과정에서 발생한 문제점을 조사 분석하여, 북핵 검증 폐기 과정 시 발생할 수 있는 문제점을 파악하고 이를 방지하기 위한 정책적 고려사항을 도출하는데 목적을 두었다.

• 공업화학
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• 제24권2호
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• pp.208-213
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• 2013

본 연구에서는 인계 난연제가 첨가된 연질 폴리우레탄 폼을 합성하여 난연제의 종류에 따른 난연성능 변화를 고찰하였다. 난연제로는 Tetramethylene bis(orthophosphorylurea) [TBPU]와 Phosphinyl alkylphosphate ester [CR-530], Resorcinol bis diphenylphosphate [RDP], Triethyl phosphate [TEP] 등을 사용하였다. 열중량분석기를 사용하여 난연제에 따른 폴리우레탄 폼의 열분해거동을 알아보았으며, 콘칼로리미터를 이용하여 열방출량, 질량감소율, 연기발생량, CO 및 $CO_2$ 발생량 등을 측정하였다. TBPU가 첨가된 폴리우레탄 폼은 난연제가 첨가되지 않은 폴리우레탄 폼에 비하여 낮은 온도에서 분해가 시작되었으나 고온에서는 많은 양의 char를 생성하였다. 콘칼로리미터 시험 결과 TBPU가 첨가될 경우 평균 발열량, 최대 발열량, 유효연소열, 질량감소율, CO 및 $CO_2$ 발생량이 감소하였고 다른 난연제에 비하여 낮은 값을 나타내어 우수한 난연성능을 나타냄을 알 수 있었다.

• 방사성폐기물학회지
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• 제20권3호
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• pp.349-356
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• 2022

Nuclear power plant decommissioning generates significant concrete waste, which is slightly contaminated, and expected to be classified as clearance concrete waste. Clearance concrete waste is generally crushed into rubble at the site or a satellite treatment facility for practical disposal purposes. During the process, workers are exposed to radiation from the nuclides in concrete waste. The treatment processes consist of concrete cutting/crushing, transportation, and loading/unloading. Workers' radiation exposure during the process was systematically studied. A shielding package comprising a cylindrical and hexahedron structure was considered to reduce workers' radiation exposure, and improved the treatment process's efficiency. The shielding package's effect on workers' radiation exposure during the cutting and crushing process was also studied. The calculated annual radiation exposure of concrete treatment workers was below 1 mSv, which is the annual radiation exposure limit for members of the public. It was also found that workers involved in cutting and crushing were exposed the most.

• 방사성폐기물학회지
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• 제21권3호
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• pp.411-417
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• 2023

During the operation of a nuclear power plant (NPP), the generation of radioactive waste, including dry active waste (DAW), concentrates, spent resin, and filters, mandates the implementation of appropriate disposal methods to adhere to Korea's waste acceptance criteria (WAC). In this context, this study investigates the potential use of polymer concrete (PC) as a high-integrity container (HIC) material for solidifying and packaging these waste materials. PC is a versatile composite material comprising binding polymers, aggregates, and additives, known for its exceptional strength and chemical stability. A comprehensive analysis of PC's long-term integrity was conducted in this study. First, its compressive strength, which is crucial for ensuring the structural stability of HICs over extended periods, was evaluated. Subsequently, the resilience of PC was tested under various stress conditions, including biological, radiological, thermal, and chemical stressors. The findings of this study indicate that PC exhibits remarkable long-term properties, demonstrating exceptional stability even when subjected to diverse stressors. The results therefore underscore the potential viability of PC as a reliable material for constructing high-integrity containers, thus contributing to the safe and sustainable management of radioactive waste in NPPs.

• 방사성폐기물학회지
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• 제9권4호
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• pp.237-245
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• 2011

후쿠시마 사고 이후 사용후핵연료 저장시설 안전성 재검증 필요성이 증대되고 있는 가운데, 재검증 결과의 신뢰성 향상을 위해 열부하 평가결과의 정확도 향상이 요구되고 있다. 이를 위한 기초연구로 본 연구에서는 상대적으로 중요성이 저평가되었던, 저장시나리오, 연소조건 관련 인자와 같이 붕괴열 및 열부하 평가 영향인자를 도출하고, 고리 4호기를 대상으로 ORIGEN2 코드를 이용해 그 효과를 평가하였다. 대표 저장시나리오에 대한 열부하 평가 결과, 최후 방출 핵연료의 붕괴열은 시나리오에 따라 전체 열부하의 최대 80.42%를 차지해 저장시설 열부하에 지배적인 영향을 미침이 확인되었다. 또한 연소조건 인자로 선택된 축 방향 연소 효과, 연소이력, 비출력 효과에 대한 민감도 분석 수행 결과, 냉각기간이 짧을수록 각 인자의 붕괴열에 대한 영향이 커지는 것으로 확인되었다. 각 인자별로는 비출력, 연소이력, 축 방향 연소 효과의 순으로 붕괴열에 대한 영향력이 컸으며, 특히 비출력의 경우 방출 직후 평균값의 0.34에서 1.66배, 방출 1년 후에는 평균 대비 0.55에서 1.37배까지 붕괴열 변화를 초래함이 확인되었다. 즉, 저장시설의 열부하 평가와 같이 냉각기간이 짧은 핵연료에 대한 해석 시 비출력, 연소이력과 같은 연소조건인자가 해석결과에 매우 큰 차이를 초래할 수 있으므로, 해석결과의 정확도 향상을 위해 기존 해석자의 공학적 판단에 의거한 임의 인자 대표성 핵연료 선택방식 대신 실제 운전 데이터의 적용 등이 필요할 것으로 보인다. 본 연구 결과는 향후 열부하 해석 결과의 정확도 향상 및 불확실도 평가를 위한 기초자료로 활용될 수 있을 것으로 사료된다.