• 해양안보
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• 제2권1호
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• pp.125-149
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• 2021

후쿠시마 원전 사고가 일어난 지 10년이 지난 지금까지도 일본은 매일 생성되는 원전 오염수 문제를 해결하지 못하고 있다. 그들은 오염수 저장탱크가 한계에 다다를 것으로 예상되자, 안전성에 관한 한국의 우려에도 일방적으로 원전 오염수를 해양에 방출하기로 했다. 문제는 한국의 대응에도 불구하고, 여전히 일본이 『유엔해양법협약』상 의무를 성실히 이행하지 않은 채 해양 방출을 준비하고 있다는 데 있다. 원전 오염수의 방사성물질로 인한 해양오염은 물론, 한국의 해양주권 침탈까지도 우려되는 상황이다. 특히 한번 환경이 오염되기 시작하면 본래의 상태로 되돌리기 어렵기에, 당장 안전성이 보장되지 않는 한 원전 오염수의 해양 방출은 반드시 막아야 한다. 본 논문은 일본과 한국이 원전 오염수 해양 방출 사안으로 빚은 갈등을 해결하기 위한 한국의 대응 전략을 제안한다. 한국은 일본과의 협력, 잠정조치, 주변국과의 공조를 통해 다양한 측면에서 일본의 원전 오염수 해양 방출에 대응해야 할 것이다.

• Journal of Radiation Protection and Research
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• 제35권1호
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• pp.6-11
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• 2010

Embodying the safety of radioactive waste disposal requires the relevant safety criteria and the corresponding stylized methods to demonstrate its compliance with the criteria. This paper proposes a conceptual model of risk-based safety evaluation for integrating complex potential radiation exposure situations in radioactive waste disposal. For demonstrating compliance with a risk constraint, the approach deals with important exposure scenarios from the viewpoint of the receptor to estimate the resulting risk. For respective exposure situations, it considers the occurrence probabilities of the relevant exposure scenarios as their probability of giving rise to doses to estimate the total risk to a representative person by aggregating the respective risks. In this model, an exposure scenario is simply constructed with three components:radionuclide release, radionuclide migration and environment contamination, and interaction between the contaminated media and the receptor. A set of exposure scenarios and the representative person are established from reasonable combinations of the components, based on a balance of their occurrence probabilities and the consequences. In addition, the probability of an exposure scenario is estimated on the assumption that the initiating external factors influence release mechanisms and transport pathways, and its effect on the interaction between the environment and the receptor may be covered in terms of the representative person. This integrated approach enables a systematic risk assessment for complex exposure situations of radioactive waste disposal and facilitates the evaluation of compliance with risk constraints.

• Nuclear Engineering and Technology
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• 제25권3호
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• pp.447-456
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• 1993

중저준위 방사성폐기물처분장 인공방벽의 핵종유출 저지능을 평가할 수 있는 단순 모델이 제안되었다. 이 모델은 현재 우리나라에서 제안되고 있는 처분장 개념을 고려하여 고안되었으며, 인공방벽의 설계에 적합한 설계 기준 유출 과 인공방벽 성능평가에 적합한 현실적 유출 두 가지 경우를 다루고 있다. 모델의 유용성을 보이기 위해 화학적 특성이 다른 다섯 핵종에 대해 모의 계산을 수행하고 그 결과를 분석하였다.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2006년도 학술논문요약집
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• pp.63-64
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• 2006

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2006년도 학술논문요약집
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• pp.219-220
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• 2006

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2005년도 춘계 학술대회
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• pp.86-86
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• 2005

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 학술대회지
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• pp.58-60
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• 2004

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 춘계학술논문요약집
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• pp.395-396
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• 2018

• Nuclear Engineering and Technology
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• 제54권12호
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• pp.4460-4473
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• 2022

The behaviour of the fission gas plays an important role in the fuel rod performance. In a previous work, we presented a physics-based model describing intra- and inter-granular behaviour of radioactive fission gas. The model was implemented in SCIANTIX, a mesoscale module for fission gas behaviour, and assessed against the CONTACT 1 irradiation experiment. In this work, we present the multi-scale coupling between the TRANSURANUS fuel performance code and SCIANTIX, used as mechanistic module for stable and radioactive fission gas behaviour. We exploit the coupled code version to reproduce two integral irradiation experiments involving standard fuel rod segments in steady-state operation (CONTACT 1) and during successive power transients (HATAC C2). The simulation results demonstrate the predictive capabilities of the code coupling and contribute to the integral validation of the models implemented in SCIANTIX.

• 방사성폐기물학회지
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• 제21권4호
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• pp.465-479
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• 2023

To ensure the safety of disposal facilities for radioactive waste, it is essential to quantitatively evaluate the performance of the waste disposal facilities by using safety assessment models. This paper addresses the development of the safety assessment model for the underground silo of Wolseong Low-and Immediate-Level Waste (LILW) disposal facility in Korea. As the simulated result, the nuclides diffused from the waste were kept inside the silo without the leakage of those while the integrity of the concrete is maintained. After the degradation of concrete, radionuclides migrate in the same direction as the groundwater flow by mainly advection mechanism. The release of radionuclides has a positive linear relationship with a half-life in the range of medium half-life. Additionally, the solidified waste form delays and reduces the migration of radionuclides through the interaction between the nuclides and the solidified medium. Herein, the phenomenon of this delay was implemented with the mass transfer coefficient of the flux node at numerical modeling. The solidification effects, which are delaying and reducing the leakage of nuclides, were maintained the integrity of the nuclides. This effect was decreased by increasing the half-life and the mass transfer coefficient of radionuclides.