• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.14 no.4
• /
• pp.385-410
• /
• 2016

The disposal facility in Gyeongju is planning to dispose of 800,000 packages of low- and intermediate- level radioactive waste. This facility will be developed as a complex disposal facility that has various types of disposal facilities and accompanying management. In this study, based on the comprehensive development plan of the disposal facility, a preliminary post-closure safety assessment is performed to predict the phase development of the total capacity for the 800,000 packages to be disposed of at the site. The results for each scenario meet the performance target of the disposal facility. The assessment revealed that there is a significant impact of the inventory of intermediate-level radionuclide waste on the safety evaluation. Due to this finding, we introduce a disposal limit value for intermediate-level radioactive waste. With stepwise development of safety case, this development plan will increase the safety of disposal facilities by reducing uncertainties within the future development of the underground silo disposal facilities.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2015.10a
• /
• pp.413-414
• /
• 2015

국내 최초로 가연성 해체폐기물 부피감용을 위해 안전하게 시설을 운영하고 있어 소각에 대한 국민인식 재고에 기여할 수 있으며, 우라늄변환시설의 가연성 해체 폐기물 소각을 통해 U 핵종오염 폐기물 소각기술을 확보하여 원자력시설 운영 효율향상, 처분비용 절감 뿐만 아니라 유해물질의 무해화로 최종처분장의 안전성 관리 최적화에 기여하고, 향후 원자력시설의 해체 및 해체 폐기물 처리/처분사업에 기술을 적극 활용할 예정이다.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2009.11a
• /
• pp.267-268
• /
• 2009

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2011.05a
• /
• pp.363-364
• /
• 2011

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2016.05a
• /
• pp.153-154
• /
• 2016

• Nuclear industry
• /
• v.5 no.2 s.24
• /
• pp.62-63
• /
• 1985

다음은 소련의 모스크바방사성폐기물처리처분센터의 개요이다. 1957년에 설립된 이 센터는 과학생산공단 소속으로서 지도 및 연구개발의 중심적 역할을 담당하는데, 이와 같은 시설은 전국 대도시 주위에 32개소가 있다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.13 no.1
• /
• pp.73-86
• /
• 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)
• /
• v.18 no.2_spc
• /
• pp.291-303
• /
• 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.

• Nuclear industry
• /
• v.36 no.9
• /
• pp.59-68
• /
• 2016

고준위 방사성폐기물의 안전 관리 문제는 모든 원자력 발전 국가들의 공통된 과제이자 아직까지도 논쟁의 중심에 서 있는 뜨거운 이슈이기도 하다. 세계 각국은 이 문제를 해결하기 위해 지난 1950년대부터 많은 노력을 해 왔다. 과연 고준위 방사성폐기물을 안전하게 처분할 수 있는 방법은 존재하는 것인지, 그리고 세계 각국은 이를 위해 어떤 노력을 하고 있고 또 어떤 생각을 갖고 있는지, 그 현황과 전망에 대해서 알아본다.

• Nuclear industry
• /
• v.33 no.3
• /
• pp.92-99
• /
• 2013

영국은 천층 처분에 부적합한 일부 저준위 방사성폐기물을 포함하여 지층 처분의 대상인 중준위 및 고준위 방사성폐기물의 효율적인 저장 관리를 위한 지침을 3년간의 방대한 노력 끝에 성공적으로 개발하여 그 결과를 최근 공개했다.