• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.583-588
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• 1996

방사성폐기물 처분후 처분장에서는 금속의 부시, 셀룰로스의 미생물분해, 방사선에 의한 분해등으로 인하여 기체가 발생하게 된다. 이 논문에서는 저준위 폐기물 수송시스템에서 고려하고 있는 폐기물모듈 개념중 6-Pack 모듈을 사용하여 치분할 때 기체발생에 미치는 영향을 평가하여 보았다. 계산은 방사성폐기물 처분장에 대한 초기 건설용량으로 고려중이었던 10만드럼 용량의 처분장을 기준으로 수행하였다. 평가결과, 6-Pack 모듈을 사용하여 처분할 때 6-pack 모듈을 사용하지 않고 처분하는 경우에 비해 H$_2$의 발생량은 1.4배 정도 증가하며, $CO_2$, CH$_4$ 등에 있어서는 영향이 거의 없는 것으로 나타났다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2006.06a
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• pp.251-252
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• 2006

원자력발전소는 기체폐기물의 90% 이상을 계획예방정비기간 중에 방출한다. 기체 폐기물 방출은 filter를 거치지 않고 대량 방출하는 고체적 방출과,filter를 거쳐 방출하는 저체적 방출이 있다. 고체적 방출은 방출농도계수가 5842, 저체적 방출은 계수가 183052로 이 이하로 방출만 하면 발전소제한구역(EPB Emergency Planning Zone)에서의 법적허용치 농도 ECL(environmental Control Limit)를 초과하지 않게 된다. 원전에서는 현재 기체방출 시 이 기준치(농도계수)의 1/10을 자체관리 기준치로 하여 적용하고 있다. 실제 울진3호기 4차O/H 시 그 실적을 파악해 본 결과 고체적 방출 시 방출농도계수가 최대 312, 저체적 방출 시는 최대 707을 넘지 않아 허용방출 농도계수와 비교하면 비교가 되지 않을 정도로 낮게 방출하였음을 확인하였다

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.316-317
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• 2004

사용후핵연료를 이용한 건식 핵연료 원격 제조 공정중 OREOX공정으로부터 핵분열기체 방출특성 평가를 위한 실험을 수행하였다. 사용후핵연료 분말화 공정인 1차 산화 및 OREOX공정에서 방출되는 핵분열기체를 실시간으로 측정할 수 있는 장치를 제작$\cdot$설치하였으며, 측정 대상 핵분열기체는 Kr-85를 포함하여 C-14$^{14}CO_2$ 형태), I-129, 기체상 트리튬 등이다. 그림 1은 방출되는 핵분열기체를 포집 또는 연속측정하기 위한 개념도이며, 그림 2는 핫셀구역에 설치된 장치 사진이다.(중략)

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.8 no.3
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• pp.229-238
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• 2010

In order to acquire a realistic forecast for the lifetime and post-closure period of the LILW (Low- and Intermediate-Level Radioactive Waste) repository and to establish the overall management plan associated gas issues. it is essential to carry out the long-term experimental research in a similar condition to actual disposal environment. Regarding this, as a part of the following-up actions on a construction and operation license for the first stage of the LILW repository at Gyeongju city, a large-scale in-situ experiment is being planned. For securing basic data on the experiment, the experimental researches related to gas generation previously performed in foreign countries are reviewed in detail. Consequently, it is judged that data on the gas generation experiment in Finland could be practically applied as the benchmark for our large-scale in-situ experiment because the same disposal concept as the Korean repository is adopted and the experiment is performed in a scale large enough to allow the use of regular waste packages.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.06a
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• pp.436-437
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• 2009

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2011.05a
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• pp.119-120
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• 2011

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.12 no.4
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• pp.267-274
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• 2014

The first Low- and Intermediate-Level Waste (LILW) disposal facility with 6 silos has been constructed in granite host rock saturated with groundwater in Korea. A two-dimensional numerical modeling on gas migration was carried out using TOUGH2 with EOS5 module in the disposal facility. Laboratory-scale experiments were also performed to measure the important properties of silo concrete related with gas migration. The gas entry pressure and relative gas permeability of the concrete was determined to be $0.97{\pm}0.15bar$ and $2.44{\times}10^{-17}m^2$, respectively. The results of the numerical modeling showed that hydrogen gas generated from radioactive wastes was dissolved in groundwater and migrated to biosphere as an aqueous phase. Only a small portion of hydrogen appeared as a gas phase after 1,000 years of gas generation. The results strongly suggested that hydrogen gas does not accumulate inside the disposal facility as a gas phase. Therefore, it is expected that there would be no harmful effects on the integrity of the silo concrete due to gas generation.

• Membrane Journal
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• v.32 no.3
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• pp.191-197
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• 2022

Ammonia nitrogen can be effectively recovered from livestock manure waste, etc. by using the gas permeable membrane technology. In this case, ammonia gas in the waste passes through the pores in one-side of membrane, impregnated in waste, and then reach the opposite side of the membrane. The permeated ammonia gas molecules are captured and recovered by acid (such as sulfuric acid) in the solution existing on the opposite side of the membrane. In order to improve ammonia nitrogen removals in the inlet part, high pH should be maintained in the feed waste including ammonia nitrogen to recover, which requires the cost of the chemical. To resolve this issue, previous studies tested various methods, for example, utilization of cheap calcium hydroxide or aeration together with inhibition of unwanted nitrification. The gas permeable membranes used for the recovery of ammonia nitrogen may be characterized, not only by proper heat and chemical resistance, but also by hydrophobicity, allowing selective ammonia gas permeation through the hydrophobic membrane pores. Future research should consider the relevant pilot or upscale processes using on-site wastes with various properties, and identify the optimal design/operation conditions as well as economic feasibility improvement plans.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.556-561
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• 2003

The quantity of the gaseous radioactive waste generated from HANARO operation for the years from 1996 to 2002 has been investigated. The amounts of Ar-41, H-3 and I-131 exhausted to the environment were 6.33E13 Bq, 5.10E12 Bq and 3.26EB Bq, respectively.

• 대한방사선방어학회:학술대회논문집
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• 2011.04a
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• pp.170-171
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• 2011