• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.261-265
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• 2003

This paper proposes acceptance requirements and the corresponding implementation strategy for the near-surface repository of low- and intermediate-level radioactive wastes. The proposed requirements include details on waste classification and radionuclide concentration limitation and inventory analysis. The strategy considers a relevant linking between predisposal waste management, disposal safety assessment and the overall disposal system.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.193-193
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• 2004

처분시설의 안정성 평가에 사용된 시나리오와 파라미터들은 본질적으로 불확실성을 가지고 있다. 이러한 불확시설성을 평가하기 위해서 동일한 시나리오에 대해서 평가 입력 파라미터의 변화에 따라 개인피폭선량 결과가 어떻게 변화하는지를 분석하였다. 본 분석에서는 처분시설을 빠져나온 핵종이 하부의 불포화된 토양층을 지나 대수층에 이른후 지하수에 의한 분산과 이류 등에 의해 인간환경의 우물까지 이동되고, 우물을 통해 다시 희석되어 부지 경계의 주민이 우물물을 식수로 사용하는 '지하수음용시나리오'가 고려되었다.(중략)

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.12 no.4
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• pp.315-334
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• 2014

Wolsong Low- and Intermediate-level radioactive waste (LILW) disposal center has two different types of disposal facilities and interacts with the neighboring Wolsong nuclear power plant. These situations impose a high level of complexity which requires in-depth understanding of phenomena in the safety assessment of the disposal facility. In this context, multidimensional radionuclide transport model and hydraulic performance assessment model should be developed to identify more realistic performance of the complex system and reduce unnecessary conservatism in the conventional performance assessment models developed for the $1^{st}$ stage underground disposal. In addition, the advanced performance assessment model is required to calculate many cases to treat uncertainties or study parameter importance. To fulfill the requirements, this study introduces the development of two-dimensional integrated near-field performance assessment model combining near-field hydraulic performance assessment model and radionuclide transport model for the $2^{nd}$ stage near-surface disposal. The hydraulic and radionuclide transport behaviors were evaluated by PORFLOW and GoldSim. GoldSim radionuclide transport model was verified through benchmark calculations with PORFLOW radionuclide transport model. GoldSim model was shown to be computationally efficient and provided the better understanding of the radionuclide transport behavior than conventional model.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.06a
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• pp.221-230
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• 2005

To support the design concept and performance evaluation of the cover system for low- and intermediate-level radioactive waste(LILW) disposal facility, the pioneering study is conducted with the tomb of historical age. Research status of the art are followed and the characteristics of tomb cover are summarized based on the preservation of historical remains. Visiting the excavation site of historical tomb and communication with Korean archeological society is required for the further understanding and for the extension of radioactive waste disposal research.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.3 no.4
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• pp.279-291
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• 2005

To support the design concept and the performance assessment of the cover system for low- and intermediate-level radioactive waste(LILW) disposal facility, a pioneering study is conducted for the tomb of historical age. Research status of the art are investigated and the characteristics of tomb cover are summarized based on the preservation status of historical remains. On-site soil samples are prepared and their unsaturated hydraulic conductivities are measured by an one-step outflow method. Visiting the excavation site of historical tomb and communication with Korean archeological society are required for the further understanding and for the extension to the radioactive waste disposal research.

• The Journal of Engineering Geology
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• v.11 no.3
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• pp.245-254
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• 2001

The experimental study on disposal cover through the performance test facility offers reliability in the safety of near surface disposal of low and intermediate level radioactive waste. To ensure the long-term safety of the repository, the impermeability, integrity, resistance to degradation and ease of maintenance might be considered as the basic performance requirement of the disposal cover. considering the difficulties to meet these performance requirement by using single layer, the disposal cover design which is composed of top layer, middle drainage layer and bottom low permeability layer is schemed for the test facility. The water balance of the cover was evaluated by using HELP code. For the long-term monitoring of the soil moisture content and matric potential, TDR probes and tensiometers will be installed in 6 test cells. Each test cell is dimensioned 3$\times$3$\times$3.3m.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.10a
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• pp.270.2-270
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• 2001

• Journal of Radiation Protection and Research
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• v.27 no.2
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• pp.111-120
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• 2002

A reference scenario of vault safety case prepared by the IAEA for the near-surface disposal facility of low-and informed]ate-level radioactive wastes is assessed with the MASCOT program. The appropriate conceptual models for the MASCOT implementation is developed. An assessment of groundwater pathway through a drinking well as a geosphere-biosphere interface is performed first. then biosphere pathway is analysed to estimate the radiological consequences of the disposed radionuclides based on compartment modeling approach. The validity of conceptual modeling for the reference scenario is investigated where possible comparing to the results generated by the other assessment. The result of this study shows that the typical conceptual model for groundwater pathway represented by the compartment model ran be satisfactorily used for safety assessment of the entire disposal system in a cons]stent way. It is also shown that safety assessment of a disposal facility considering complex and various pathways would be possible by the MASCOT program.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.06a
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• pp.274-275
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• 2005

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2010.10a
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• pp.155-156
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• 2010