• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.13 no.1
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• pp.73-86
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• 2015

The use of complimentary indicators, other than radiation dose and risk, to assess the safety of radioactive waste disposal has been discussed in a number of publications for providing the reasonable assurance of disposal safety and convincing the public audience. In this study, the radionuclide flux was selected as performance indicator to appraise the performance of engineered barriers and natural barrier in the Wolsong low- and intermediate-level waste disposal facility. Radionuclide flux showing the retention capability by each compartment of the disposal system is independent of assumptions in biosphere model and exposure pathways. The scenario considered as the normal scenario of disposal facility has been divided into intact or degraded silo concrete conditions. In the intact silo concrete, the radionuclide flux has been assessed with respect to the radionuclide retardation performance of each engineered barrier. In the degraded silo concrete, the radionuclide flux has been explored based on the performance degradation of engineered barriers and the relative significance of natural barrier quantitatively. The results can be used to optimally design the near-surface disposal facility being planned as the second project phase. In the future, additional complimentary indicators will be employed for strengthening the safety case for improving the public acceptance of low- and intermediate-level waste disposal facility.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.4
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• pp.347-356
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• 2008

The purpose of Radioactive Waste Acceptance Criteria(WAC) is to verify a radioactive waste compliance with radioactive disposal facility requirements in order to maintain a disposal facility's performance objectives and to ensure its safety. To develop WAC which is conformable with domestic disposal site conditions, we furthermore analysed the WAC of foreign disposal sites similar to the Kyung-Ju disposal site and the characteristics of various wastes which are being generated from Korea nuclear facilities. Radioactive WAC was developed in the technical cooperation with the Korea Atomic Energy Research Institute in consideration of characteristics of the wastes which are being generated from various facilities, waste generators' opinions and other conditions. The established criteria was also discussed and verified at an advisory committee which was comprised of some experts from universities, institutes and the industry. So radioactive WAC was developed to accept all wastes which are being generated from various nuclear facilities as much as possible, ensuring the safety of a disposal facility. But this developed waste acceptance criteria is not a criteria to accept all the present wastes generated from various nuclear facilities, so waste generators must seek an alternative treatment method for wastes which were not worth disposing of, and then they must treat the wastes more to be acceptable at a disposal site. The radioactive disposal facility WAC will continuously complement certain criteria related to a disposal concentration limit for individual radionuclide in order to ensure a long-term safety.

• Proceedings of the Korean Society for Rock Mechanics Conference
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• 2006.03a
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• pp.205-213
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• 2006

본고에서는 해외사례의 조사/분석을 통해 국내 환경에 적합한 처분시스템을 개발하는데 효율적으로 이용할 목적으로 일본의 방사성 폐기물 처분과 관련한 주요기관의 사업내용을 정리하고 암석역학 전공자가 관심을 가져볼 만한 처분 관련 연구시설 및 연구내용을 소개한다. 저준위 폐기물을 대상으로 한 100m 심도의 롯까쇼무라 시험공동과 고준위 폐기물을 대상으로 결정암질에 건설되는 1000m 심도의 미즈나미 지하연구시설 및 퇴적암질에서의 500m 심도의 호로노베 지하연구시설을 소개하였다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.4
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• pp.387-398
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• 2008

To obtain base-line data in the low- and intermediate-level radioactive waste disposal facility, radiological environment investigation is required at least two years prior to the facility operation near the disposal facility. The investigation has been performed since January 2007 for the Wolsong LILW disposal center. In this paper, investigation procedure and detailed information obtained for six months in 2008 are described. Based on the current results, future investigation planning is also discussed for the radiological environment management of the disposal facility.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.199-207
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• 2004

In order to develop a safe geological disposal concept for the HLW from the nuclear power plants in Korea, it is necessary to evaluate the safety of the disposal concept in an underground research tunnel in the same geological formation as the host rock mass. The design concept of a research tunnel depends on the actual disposal concept, repository geometry, experiments to be carried at the tunnel, and geological conditions. In this study, geological investigation had been carried out to develop the basic design of the small scale underground disposal research tunnel in KAERI.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.239-243
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• 2003

Environmental monitoring program is investigated based on Atomic Energy Law and foreign country radiation monitoring programs on low-and intermediate level radioactive waste disposal site. It is anticipated that the number of radiation measurements and samples will be higher than those of NPP's. The radiation monitoring program on LLW disposal site should be well prepared reflecting PA, site characteristics and regulation.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.5 no.3
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• pp.239-255
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• 2007

An underground research tunnel is essential to validate the integrity of a high-level waste disposal system, and the safety of geological disposal. In this study, KAERI underground research tunnel(KURT) was constructed in the site of Korea Atomic Energy Research Institute(KAERI). The results of the site investigation and the design of underground tunnel were presented. The procedure for the construction permits and the construction of KURT were described briefly. The in-situ experiments being carried out at KURT were also introduced.

• 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.2 no.4
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• pp.279-292
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• 2004

The underground research tunnel is essential to validate the integrity of a reference high-level waste disposal system, and the safety of geological disposal. In this study, a basic design of an underground research tunnel (URT) was tried to be developed. The candidate site for URT was described briefly, and it was intended to suggest the basic concept of the underground research tunnel. In order to develop the design of URT based on the basic concept, design requirements were established. Based on the basic concept and the design requirements, the basic design of URT was performed. Research items to be studied in the URT were also derived in this study.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.175-187
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• 2004

This paper reviews basic considerations for establishing managerial requirements on the domestic low- and intermediate-level radioactive waste repository and presents the corresponding draft requirements. The draft emphasizes their close linking with the related regulations, standards and safety assessment for the repository. It also proposes a desirable direction towards harmonizing together with the existing waste acceptance requirements for the repository