전 세계적으로 RNA 간섭(RNA interference, RNAi)을 활용한 해충방제제 연구가 활발히 진행되고 있다. 대표적 으로 Monsanto의 서부 옥수수 뿌리벌레(Diabrotica virgifera virgifera) 특이적 방제용 dsRNA (DvSNF7)를 발현하 는 옥수수 종자가 상용화 되었고, 2016년 이 종자가 국내 사료 및 식품용으로 수입이 승인 되었다. 본 연구는 국내 에 서식하는 좁은가슴잎벌레(Phaedon brassicae)를 Non-target 곤충으로 사용하여, 옥수수 종자에 사용된 DvSNF7 dsRNA의 잠재적 위해성을 평가했다. P. brassicae의 SNF7 유전자와 DvSNF7 dsRNA 간 Sequence유사성 을 확인했다. 다음으로 P. brassicae가 DvSNF7 dsRNA를 섭식할 수 있는 환경을 조성하여, 치사 효과 실험과 Sequence특이적인 Knockdown효과를 확인하였다. 그 결과, DvSNF7 dsRNA는 P. brassicae생존에 영향을 미치지 않았으며, P. brassicae의 SNF7유전자를 Knockdown시키지 않음을 확인했다. 이번 연구를 통해 D. virgifera virgifera와 같은 과인 P. brassicae 는 SNF7유전자 간 Sequence유사성이 있지만, Sequence특이성이 부족하여 생존과 유전자 발현에 영향을 주지 않음으로써 위해성이 낮음을 확인했다.

생물다양성협약 당사국총회 결의에 따르면, 환경영향평가란 제안된 계획 또 는 개발이 환경에 미칠 것 같은 영향을 이익적 측면과 불리한 측면에서 사회경 제적, 문화적 및 인간의 건강에 미치는 영향과 연계하여 평가하는 과정을 의미한다. 해양에서의 환경영향평가 제도는 다수의 국가에 의해 국내법적으로 수용 하여 수행되어왔으며, 국제적으로도 많은 환경협약과 하위 지침들로부터 의무 화하여 수행되고 있다. 국제법상 국가관할권 이원지역에 대한 환경영향평가의 수행의무는 분명히 존재한다. 최근 채택된 BBNJ협정은 국가관할권 이원지역에 대한 종합적인 환경 및 해양생물다양성 보호를 목적으로 하는데, 그중 제4부는 환경영향평가의 발동요건, 절차, 평가의 내용, 협의과정, 의사결정 등 환경영향 평가 수행 전반에 대한 요건을 서술하고 있다. 본 연구에서는 다수의 환경영향 평가와 관련된 기존제도들 중 국가관할권 이원지역만을 협약의 적용지역으로 하고, 명확히 환경영향평가의 의무를 부과하고 있는 남극조약체제 및 국제해저 기구 주관하의 심해저 광업규칙상 환경영향평가제도와 BBNJ협정상 환경영향 평가제도의 비교를 통해 환경보호의 대응기조가 어떻게 유사하게 반영되었는 지 또는 차이점이 있는지 살펴보고 그 실효성에 대하여 논한다. 결론적으로 1) 기존제도와 달리 BBNJ협정은 call-in mechanism의 적용을 통 해 환경영향평가서에 대한 최종 의사결정권을 당사국에게 부여하고 있다. 2) 국가관할권 내측 지역으로부터의 월경 오염에 대한 환경영향평가 절차를 포함 함으로써 월경오염에 대한 준수의 효과성을 보장하고자 하였다. 3) 대중통고 및 협의, 활동의 영향에 대한 검토 조항을 통해 환경영향평가의 절차에서 넓은 범위의 이해관계자를 포함하고, 기존제도와 달리 국가관할권 이원지역에서의 활동으로부터 야기된 월경오염으로 영향을 받을 수 있는 연안국을 명시하여 환 경영향평가 절차에서 역할을 부여하고 있다. 4) 기존제도상 환경영향평가시 고 려되던 누적영향 및 잔존영향에 더하여 전략환경평가라는 현대적 보전기법을 규정하고 있다. 남극조약체제 및 국제해저기구 주관하의 심해저 광업규칙상 환 경영향평가제도 역시 과거 작성되었던 규칙에 대비하여 비교적 최근의 규칙 및 현재 작성중인 문서에서 대중통고 절차 신설, 확장된 이해관계자의 참여 근거 규정 마련 등에 따라 환경보호를 위한 국제사회의 강화된 기조에 대응하고 있 음을 살펴볼 수 있었다. 향후 당사국 총회를 통해 환경영향평가의 세부 지침이 보완될 것임에 따라, 기존의 관련 제도상 환경영향평가 절차 및 내용에 대한 정확한 숙지를 기반으로 하여 대응해 나가야 할 것이다. 또한 관련 전문기관을 지정하고 과학 전문가 양성에 집중해야 할 것이다.

Herbicide-resistant transgenic rapeseed (TG rapeseed) was developed by inserting phosphinothricin acetyltransferase (PAT, bar), a modified gene from the soil bacterium Streptomyces hygroscopicus, into the genome of a conventional variety of rapeseed (Youngsan). The TG rapeseed used for the test was confirmed to express the PAT gene by polymerase chain reaction (PCR) and immunostrip. Feeding tests were conducted with Cyprinus carpio to evaluate the environmental risk of TG rapeseed, including the herbicide resistant gene. C. carpio was fed 100% ground rape suspension, TG rapeseed, or non-genetically modified (GM) counterpart rapeseed (Youngsan). As a result, the feeding test showed no significant differences in the cumulative immobility or abnormal response between C. carpio samples fed on TG rapeseed and non-GM counterpart rapeseed. The 48 h-LC50 values of the TG rapeseed and the non-GM counterpart rapeseed were 3,376 mg/L (95 % confidence limits: 3,169 - 3,596 mg/L) and 2,682 mg/L (95 % confidence limits: 2,267 – 3,123 mg/L), respectively. The rape NOEC (no observed effect concentration) value for C. carpio was suggested to be 625 mg/L. Based on these results, there was no significant difference in the toxicity for non-target organisms (C. carpio) between the TG rapeseed and non- GM counterparts.

Domestic nuclear power plants conduct radiological environmental impact assessments every year in accordance with the Nuclear Safety and Security Commission (NSSC) notice. Among them, gaseous effluents are evaluated for their effects due to inhalation, external exposure in the air, exposure from ground surface deposits, food intake. In order to evaluate the impact of this exposure pathway, an evaluation point for each pathway must be selected. In the case of evaluation points, each country has different evaluation points. In the case of Korea, the evaluation point is calculated on the assumption that one lives 365 days a year at the EAB and consumes food from the nearest production area. In the case of the United States, external exposure and inhalation are evaluated at the site boundary or the nearest residential area, and food intake is evaluated by assuming that food produced in the nearest residential area or the nearest production area is consumed. Currently, the dose evaluation is optimized and selected so that EAB evaluation point for each site includes 16 direction evaluation points for each unit. In the E-DOSE60 program currently under development, the evaluation point was selected by calculating 16 direction x number of units without optimization. The food intake evaluation point was selected as the point that satisfies the minimum farmland area of the U.S. NRC NUREG-1301 and is the shortest distance from the site. The location of the production point from multiple units in included all 16 directions for each unit and quantity of evaluation points was optimized to satisfy the shortest distance. It can contribute to improving the reliability of the E-DOSE60 program currently under development by selecting new evaluation points for evaluating inhalation and external exposure evaluation and selecting optimized dose evaluation points for each site for evaluation by ingestion.

In Korea, Kori Unit 1 and Wolsong Unit 1, have been permanently shut down in 2017 and 2019, and more nuclear power plants are expected to be permanently shut down after continued operation successively. Spent fuel has been generated during operation and stored in spent fuel pools. Due to the expected saturation of spent fuel pools within the next several decades, transportation of a huge amount of spent fuel is anticipated to interim storage facilities or final disposal facilities, even though the specific location is not decided. The U.S. Nuclear Regulatory Commission (NRC) states that every environmental report prepared for the licensing stage of a Pressurized Water Reactor shall contain a statement concerning risk during the transportation of fuel and radioactive wastes to and from the reactor. Thus, the licensee should ensure that the radiological effects in accidents, as well as normal conditions in transport, do not exceed certain criteria or be small if cannot be numerically quantified. Specific conditions that a full description and detailed analysis of the environmental effects of transportation of fuel and wastes to and from the reactor are exempted are specified in 10 CFR Part 51. Since there are no official requirements for radiological dose assessment for workers and public during the transportation of spent fuel in Korea, the margin when applying the U.S. regulatory criteria to the environmental impact assessment during the transport of spent fuel generated from domestic nuclear power plants is evaluated. A different approach would be needed due to the difference in the characteristics of spent fuel and geographical features.

우리나라 해양환경에 유출되는 위험·유해물질(Hazardous Noxious Substances, HNS)의 해양환경 및 사회환경 영향평가 결과 와 HNS 확산 영역, 해양환경 정보, HNS 실태조사 결과 등 관련 연구 결과 및 자료를 정책결정자와 연구자들에게 공유할 수 있는 HNS 국내 용 플랫폼을 구축하고자 한다. 국내의 HNS 관리 및 배출 체계 마련을 위한 의사결정 지원이 가능하고 국내 실정에 적합한 플랫폼의 설계 를 위하여 유해물질의 데이터 관리 및 유출 시 대응 도구, 기초적인 정보 등 플랫폼에 관련된 기술동향을 분석하는 등 국내·외의 플랫폼 개발 사례를 고찰하였다. 유속 벡터의 전처리 기능 개발, 전처리 결과에 따른 동적 시각화 구현, 해양산업시설 배출 HNS의 유출량과 유출 범위의 전처리 모듈, HNS 해양환경 영향평가 연산 모듈 프로토타입을 개발하였다. HNS 해양환경 영향평가를 위한 국내용 HNS 플랫폼은 초기 위해성을 평가하고 대응 및 관련 법제화 시 과학적인 기초 도구로써 활용될 수 있을 것으로 기대된다.

The US NRC developed a program called NRCDose3 to evaluates the environmental impact of radiation around nuclear facilities. The NRCDose3 code is a software suite that integrates the functionality of three individual LADTAP II, GASPAR II, and XOQDOQ Fortran codes that were developed by the NRC in the 1980’s and have been in use by the nuclear industry and the NRC staff for assessments of liquid effluent and gaseous effluent, and meteorological transport and dispersion, respectively. Through the integrated program, it is possible to conduct safety assessment and environmental impact assessment from liquid and gaseous effluent when operating permits are granted. In addition to a more user-friendly graphic user interface (GUI) for inputting data, significant changes have been made to the data management and operation to support expanded capabilities. The basic calculation methods of the LADTAP II, GASPAR II, and XOQDOQ have not been changed with this update to the NRCDose3 code. Several features have been added. The previous program used only ICRP-2 dose conversion factor, but the new program can additionally use dose conversion factor of ICRP-30 and ICRP-72. In the previous program, 4 age groups (infant, child, teen, and adult) were evaluated during dose evaluation, but when ICRP-72 was selected, 6 age groups (infant, 1-year, 5-year, 10-year, 15-year, and adult) could be evaluated. In addition, when selecting ICRP-72, many user-modifiable parameters such as food intake and exposure time were added. It will be referred to E-DOSE60, a program currently under development.

After the Fukushima nuclear power plant accident in 2011, interest in technology for evaluating residents’ exposure to effluents generated from nuclear power plants at the time of the accident has increased. KHNP has developed the S-REDAP program and is using it to evaluate radiation dose and recommend resident protection measures in the event of a nuclear power plant emergency. Its main functions are source term evaluation, atmospheric diffusion evaluation, radiation dose evaluation, etc. Based on these evaluations, resident protection measures are evaluated. In Japan, evaluation is conducted through a program called SPEEDI-MP (System for Prediction of Environmental Emergency Dose Information Multi-model Package) created by JAEA (Japan Atomic Energy Agency). Similar to S-REDAP, the program also evaluates effluents emitted from nuclear facilities through source term evaluation and atmospheric diffusion factor evaluation. In JAEA, through a program using SPEEDI-MP, the source term evaluation was performed in collaboration with NSC (Nuclear Safety Commission) in the event of the Fukushima nuclear plant accident, and dose evaluation in Japan was performed 2 months as an atmospheric diffusion factor using meteorological data for 2 days. Through comparative analysis of evaluation data from Japan, improvements to the current program be derived.

K-DOSE60, a off-site dose calculation program currently used by khnp, is performing evaluation based on the gaseous effluent evaluation methodology of NRC Reg. Guide 1.109. In particular, H-3 and C-14, which are the major nuclides of gaseous effluent, are evaluated using a ratio activity model. Among them, H-3 is additionally evaluating the dose to OBT (Organically Bound Tritium) and HT as well as HTO (Triated water). However, NRC Reg. Guide 1.109 is a methodology developed in the 1970s, and verification was performed by applying the evaluation methodology of H-3 and C-13 presented by IAEA TRS-472 in 2010 to the current K-DOSE60. The IAEA TRS-472 methodology also includes OBT and HT for H-3. In order to apply the ratio radioactivity model presented in IAEA TRS-472, the absolute and relative humidity were calculated using the weather tower of the nuclear site and used for H-3 evaluation. For the dose evaluation of HT, the previously used Canada Chalk River Lab. (CNL) conversion factor was used. For atmospheric carbon concentration, the carbon concentration presented in IAEA TRS-472 was used, not the carbon concentration in the 1970s of NRC Reg. Guide 1.109. It was confirmed that the K-DOSE60, which applied the changed input data and methodology, was satisfied by performing comparative verification with the numerical calculation value.

In 2022 and 2023, the Korea Institute of Nuclear Safety (KINS), a regulatory body, revised the regulatory guidelines for off-site dose evaluation to residents, marine characteristics surveys around nuclear facilities, and environmental radiation surveys and evaluation around nuclear facilities. In addition, the NRC, a US regulatory body, has revised regulatory guide 1.21 (MEASURING, EVALUATING, AND REPORTING RADIOACTIVE MATERIAL IN LIQUID AND GASEOUS EFFLUENTS AND SOLID WASTE) to change environmental programs for nuclear facilities. The domestic regulatory guidelines were revised and added to reflect the experience of site dose evaluation for multiple units during the operation license review of nuclear facilities, the resident exposure dose age group was modified to conform to ICRP-72, and the environmental monitoring plan was clarified. In the case of the US, the recommended guidelines for updating the long-term average atmospheric diffusion factor and deposition factor, the clarification of the I-131 environmental monitoring guidelines for drinking water, and the clarification of the procedures described in the technical guidelines when changing environmental programs have been revised and added. Through such regulatory trend review, it is necessary to preemptively respond to changes in the regulatory environment in the future.

We deduced the proper estimation methodology for the amount of carbon sequestration by damaged trees for Environmental Impact Assessment (EIA). The nine development projects related to renewable energy, damaged trees occur, assessment status and used method of evaluating the carbon storage of damaged trees were summarized. And after re-calculating the carbon storage of damaged trees through allometric equations, the difference between the two groups, re-calculated the damaged trees carbon storage and the damaged trees carbon storage in the report, was validated. As a result, damaged trees carbon storage in words was more than the re-calculated damaged trees carbon storage, and it was statistically significant (p<0.005). This result means that the existing method for calculating damaged tree carbon storage is overcalculated. It was judged that it was necessary to improve the calculation method. Therefore, allometric equations suitable for each dominated-tree species should be used when calculating the damaged tree carbon storage. Furthermore, we propose to establish a carbon storage calculation system based on actual data from the ecosystem so that researchers can efficiently and accurately the damaged trees carbon storage. Key words: damaged vegetation, carbon sequestration, allometric equation, environmental impact

미역(Undaria pinnatifida) 포자를 사용한 생태독성 시험법은 연중 상시 이용하기에 어렵다. 미역 의 암배우체는 실험실에서 배양할 수 있기 때문에, 포자의 단점을 보완하고 상시 생태독성 시 험에 사용할 수 있다. 따라서 미역의 암배우체를 생태독성 시험에 활용하기 위해 다양한 환경 조건에 노출된 미역의 암배우체 생존율과 상대성장률의 변화를 분석하였다. 미역 암배우체는 염분(5~40 psu), 온도(5~30℃), pH (2~10), 광량(0~120 μmol photon m-2 s-1)에 노출되었다. 암배 우체의 생존율은 최고 평균값을 기준으로 온도 20℃, 염분 27.5 psu, pH 8, 광량 30 μmol photon m-2 s-1에서 가장 높았다. 상대성장률은 최고 평균값을 기준으로 온도 15℃, 염문 35 psu, pH 9, 광량 60 μmol photon m-2 s-1에서 가장 높았다. 본 연구결과를 통해 미역 암배우체의 생존율과 상대성장률을 활용하여 연안환경을 상시 신속하게 평가하기 위한 효율적인 방법으로 활용이 기대된다.

Recently, the construction of tall buildings utilized by high strength-concrete in the whole world is tending to be on the rise. The application of high-rise structural system in buildings results in the excellent cut-down effect in construction materials due to section reduction. Therefore, in order to investigate the CO2 and resource reduction effect for the high-rise structural system, comparisons of GWP and ADP in embodied energy of structural materlais between 4 type of high-rise structural system have been performed. As a result, GWP emission increased in the order of steel structure outrigger system, RC shear wall system, and RC outrigger system. On the other hand, ADP emissions increased in the order of RC shear wall system, RC outrigger system, and steel structure outrigger system.

The U.S. Nuclear Regulatory Commission (NRC) states that every environmental report prepared for the licensing stage of a Pressurized Water Reactor shall contain a statement concerning risk during the transportation of fuel and radioactive wastes to and from the reactor. Thus, the licensee should ensure that the radiological effect in accidents, as well as normal conditions in transport, do not exceed certain criteria or be small if cannot be numerically quantified. These are specified in 10 CFR Part 51 and applied in NUREG-1555 Supplement 1 Revision 1, which deals with Environmental Standard Review Plan. Corresponding regulations in Korea would be the Nuclear Safety and Security Commission Notice No. 2020-7. In Appendix 2 of the Notice, guides on the radiological environmental report for production and utilization facilities, spent nuclear fuel interim storage facilities, and radioactive waste disposal facilities. In this guide, unlike the regulations in the U.S., there are no obligations for radiological dose assessment for workers and public during the transportation. Therefore, overall regulations and their legal basis related to risk assessment during transportation conducted for the environmental report in the U.S. were analyzed in this study. On top of that, through the comparison with regulations in Korea, differences between the two systems were figured out. Finally, this study aims to find the points in terms of assessing transport risk to be revised in the current regulatory system in Korea.

양식장 환경관리를 위하여 여러 나라에서 양식장 환경관리시스템을 구축하고 있으며, 어장환경평가가 그중 하나이다. 2013년에 개정된 국내 어장관리법에는 어류가두리양식장 면허를 연장할 때 어장환경평가를 받도록 명시되어 있다. 어장환경평가는 과학적 분석을 통한 평가를 바탕으로 양식장 환경 개선 조치를 실행하여, 지속 가능한 어업생산 조성, 어장 생산력 증가, 어업인의 소득 증가를 목적으로 한다. 어장환경평가의 평가지표는 저서다모류 군집을 기초로 한 생물지수인 저서동물지수(BHI)와 총유기탄소량(TOC)이며, 두 항목을 점 수화하여 단일등급으로 산출하여 평가에 사용한다. 본 연구는 어장환경평가지표인 BHI와 TOC의 선정 과정과 산출된 평가 등급의 생태학 적 의미를 설명한다.