Recently, BNS (Best System) developed a system for evaluation and classification of soil and concrete wastes generated from nuclear power plant decommissioning. It is composed of various modules for container loading, weight measurement, contamination evaluation, waste classification, stacking, storage and control. The contamination evaluation module of the system has two sub modules. One is for quick measurement with NaI (Tl) detector and the other is for accurate measurement with HPGe detector. The container used at the system for wastes handling has capacity of 100 kg and made of stainless steel. According to the measurement result of Co-60 and Cs-137, the waste is classified as waste for disposal or waste for clearance. Performance of the system was demonstrated using RM (Reference Material) radiation source. This year, necessity of system improvement was suggested due to revised operation requirements. So, the system should show throughput of more than 1 ton/hr and Minimum Detectable Activity (MDA) of less than 0.01 Bq/g (1/10 of criteria for regulatory clearance) for Co-60 and Cs-137. And soil waste become main target of the system. For this, the container used for soil waste handling should have capacity of 200 kg. As a result, material for the container need to be changed from stainless steel to plastic or FRP (Fiber Reinforced Plastics). And large area detector should be introduced to the system to enhance processing speed of the system. Additionally, container storage rack and conveyor system should be modified to handle 200 kg capacity container. Finally, moving path of the container will be redesigned for enhanced throughput of the system. In this paper, concept development of the system was suggested and based on that, system development will be followed.

Radioactive liquid waste generated during the operation of domestic nuclear power plants is treated through a somewhat different liquid radwaste system (LRS) for each plant. Prior to the introduction of standard nuclear power plants, LRS used a concentrated water dry system (CWDS) to evaporate liquid waste and manage it in the form of dry powder. The boron-containing radioactive liquid waste dry powder was solidified using paraffin from 1995 to 2010, and about 3,650 drums (based on 200 L) of paraffin solidified drums are currently stored in nuclear power plants. Paraffin solidification drums do not meet the acceptance criteria for radioactive waste repositories because it is difficult to secure the homogeneity of the solidified body and there are concerns about leaching of radioactive waste due to the low melting point of paraffin. In order to solve this problem and safely permanently dispose of paraffin solidification drums, the characteristics of dry powder paraffin solidification drums containing boron-containing radioactive liquid waste must be analyzed and appropriate treatment technology utilizing the results must be introduced. This study analyzes the physical properties of paraffin, the chemical properties of boron-containing radioactive waste dry powder, and the physicochemical properties of paraffin solidification powder, and proposes an appropriate alternative technology for treating boron-containing radioactive waste dry drum. When disposing of the paraffin solidification drum with boron-containing radioactive liquid waste dry powder, the solidification body must be effectively withdrawn from the drum and the paraffin must be completely separated from the solidification body. When disposing the drum, the solidified material must be effectively extracted from the drum and the paraffin must be completely separated from the solidified material. Afterwards, the paraffin must be self-disposed, and the radioactive waste must be disposed of in accordance with acceptance criteria of repository. We looked at how each characteristic of the paraffin solidification drum with boron-containing radioactive liquid waste dry powder can be utilized in each of the above treatment processes.

Dry active wastes (DAWs) are combustible waste generated during the operation and decommissioning of nuclear facilities, and are known to be generated in the amount of approximately 10,000 to 40,000 drums (based on 200 L) per unit. It consists of various types of protective clothing, paper, and plastic bags, and is stored in radioactive waste storage facilities. Therefore, reducing the volume of DAWs is an important issue in order to reduce storage costs and utilize the limited space of waste storage facilities. Heat treatment such as incineration can dramatically reduce the volume of waste, but as the waste is thermally decomposed, CO2, a global warming gas, is generated and there is a risk of emissions of harmful gases including radionuclides. Therefore, a heat treatment process that minimizes the generation of CO2 and harmful gases is necessary. One of the alternatives to incineration is to carbonize DAWs, dispose of carbonized materials below the release standard as non-radioactive waste, and selectively separate and stabilize inorganic components, including radionuclides, from carbonized DAWs. In this study, 13 types of DAWs generated from nuclear power plants were selected and their thermal decomposition characteristics were investigated to design a heat treatment process that replaces incineration. As a result of TGA analysis, the temperature at which thermal decomposition of each waste begins is 260-300°C for cotton, 320-330°C for paper, 315-420°C for synthetic fiber, 350°C for latex gloves. The mass of most samples decreased to less than 1 % of the initial weight after heat treatment, and dust suit and latex gloves had residues of 13.83% and 13.71% of the initial mass, respectively. The metal components of the residue produced after heat treatment of the sample were analyzed by EDS. According to the EDS results, cotton contains Ca and Al, paper contains Ca, Al and Si, synthetic fiber contains Ca, Cu and Ti, latex gloves contain Ca and Mg. Additionally, ICP analysis was performed to quantify the inorganic components. These results are expected to be applicable to the processing of DAW generated at nuclear facilities in the future.

There is a large amount of radioactive waste in waste storage in the Korea Atomic Energy Research Institute. Some of the radioactive waste was generated during the dismantling process due to Korea Research Reactor 1&2 and it accounts for 20% of the total waste. Radioactive waste must be reduced by appropriate disposal methods to secure storage space and to reduce disposal costs. Research Reactor wastes include wastes that are below the acceptable criteria for selfdisposal and non-contaminated wastes, so they can be treated as wastes subject to self-disposal through contamination analysis and reclassification. In order to deregulation radioactive waste, it is necessary to meet the self-disposal standards stipulated in the Domestic Nuclear Act and the treatment standards of the Waste Management Act. The main factors of deregulation are surface contaminant, radionuclide activity and dose assessment. To confirm the contamination of waste, surface contaminant and gamma nuclide analysis were performed. After homogenizing the waste sample, it was placed in 1 L Mariinelli beaker. When collecting waste samples, 1 kg per 200 kg of waste was collected. The concentrations of the major radionuclides Co-60, Cs-134, Cs-137, Eu-152, and Eu-154 were analyzed using HPGe detector. To evaluate radiation dose, various computational programs were used. A dose assessment was performed with the analyzed nuclide concentration. The concentrations of representative nuclides satisfied the deregulation acceptance criteria and the results of the dose assessment corresponding to self-disposal method was also satisfied. Based on this results, KAERI submitted the report on waste self-disposal plan to obtain approval. After final approval, Research Reactor waste is to be incinerated and incineration ash is to be buried in the designated place. Some metallic waste has been recycled. In this study, the suitability of deregulation for self-disposal was confirmed through the evaluation of the surface contaminant analysis, radionuclide concentration analysis and dose assessment.

The HADES (High-level rAdiowaste Disposal Evaluation Simulator) was developed by the Nuclear Fuel Cycle & Nonproliferation (NFC) laboratory at Seoul National University (SNU), based on the MOOSE Framework developed by the Idaho National Laboratory (INL). As an application of the MOOSE Framework, the HADES incorporates not only basic MOOSE functions, such as multi-physics analysis using Finite Element Method (FEM) and various solvers, but also additional functions for estimating the performance assessment of Deep Geological Repositories (DGR). However, since the MOOSE Framework does not have complex mesh generation and data analyzing capabilities, the HADES has been developed to incorporate these missing functions. In this study, although the Gmsh, finite element mesh generation software, and Paraview, finite element analysis software, were used, other applications can be utilized as well. The objectives of HADES are as follows: (i) assessment of the performance of a Spent Nuclear Fuel (SNF) disposal system concerning Thermal-Hydraulic-Mechanical-Chemical (THMC) aspects; (ii) Evaluation of the integrity of the Engineered Barrier System (EBS) of both general and high-efficiency design perspective; (iii) Collaboration with other researchers to evaluate the disposal system using an open-source approach. To achieve these objectives, performance assessments of the various disposal systems and BMTs (BenchMark Test), conducted as part of the DECOVALEX projects, were studied regarding TH behavior. Additionally, integrity assessments of various DGR systems based on thermal criteria were carried out. According to the results, HADES showed very reasonable results, such as evolutions and distributions of temperature and degree of saturation, when compared to validated code such as TOUGH-FLAC, ROCMAS, and OGS (OpenGeoSys). The calculated data are within the range of estimated results from existed code. Furthermore, the first version of the code, which can estimate the TH behavior, has been prepared to share the contents using Git software, a free and open-source distribution system.

A comparison and validation between the analysis and vibration test data of a nuclear fuel assembly were conducted. During the comparison and validation process, various parameters that govern the vibration behavior of the fuel assembly were determined, including nuclear fuel rod’s stiffness, spring constants of the dimple and spring of support structures, and damping coefficients. The calibration of the vibration analysis model aimed to find analysis parameters that can accurately simulate the vibration behavior of the test data. For calibration, power spectral density (PSD) diagrams were generated for both the measured signals from the test and the calculated signals from the analysis. The correlation coefficient between these two PSD plots was calculated. To find the analysis parameters, each parameter was defined as a variable with an appropriate range. Latin hypercube sampling was used to generate multiple sample points in the variable space. Analysis was performed for the generated sample points, and PSD plot correlation coefficients were calculated. Using the generated sample points and their corresponding results, a Gaussian Process Regression model was implemented for PSD plot correlation coefficients and the maximum PSD value. Based on the constructed surrogate model, the optimal analysis parameters were easily found without additional computations. Through this method, it was confirmed that the analysis model using the optimal parametes appropriately simulates the vibration behavior of the test.

Currently, the development of evaluation technology for vibration and shock loads transmitted to spent nuclear fuel and structural integrity of spent nuclear fuel under normal conditions of transport is progressing in Korea by the present authors. Road transportation tests using surrogate spent nuclear fuel were performed in September, 2020 using a test model of KORAD-21 transportation cask and sea transportation tests were conducted from September 30 to October 4, 2021. Finally, the shake table tests and rolling test were conducted from October 31 to November 2, 2022. As a result of the sea transportation test data analysis, an impact load resulting from the collision of objects was measured on fuel rods of a surrogate spent nuclear fuel assemblies during the rolling test was observed. Excessive rolling motion occurred on the ship during the rolling test, causing the surrogate spent nuclear fuel assemblies to slip and collide with the canister. To analyze under which conditions such impact loads occur and whether this event is possible under normal conditions of transport of spent nuclear fuel, a test was designed to simulate the rolling test in sea transportation and was performed. The rolling test was conducted on ACE7 and PLUS7 assemblies, respectively, varying the rolling angle and rolling frequency to determine at which angles and frequencies the assemblies experienced slippage. According to the test results, slippage of the used nuclear fuel assemblies can occur due to rolling motion at angles of approximately 14° or higher, leading to the possibility of generating impact loads. It was observed that the rolling angle is a more major factor for slippage than the rolling frequency. This exceeds the conditions under which a vessel can be permitted to depart for coastal navigation, thus it is considered to deviate from the normal conditions of transport of spent nuclear fuel. Therefore, it is not necessary to consider such loads for evaluating the integrity of spent nuclear fuel during normal transportation conditions.

To address the pressing societal concern in Korea, characterized by the imminent saturation of spent nuclear fuel storage, this study was undertaken to validate the fundamental reprocessing process capable of substantially mitigating the accumulation of spent nuclear fuel. Reprocessing is divided into dry processing (pyro-processing) and wet reprocessing (PUREX). Within this context, the primary focus of this research is to elucidate the foundational principles of PUREX (Plutonium Uranium Redox Extraction). Specifically, the central objective is to elucidate the interaction between uranium (U) and plutonium (Pu) utilizing an organic phase consisting of tributyl phosphate (TBP) and dodecane. The objective was to comprehensively understand the role of HNO3 in the PUREX (Plutonium Uranium Redox Extraction) process by subjecting organic phases mixed with TBPdodecane to various HNO3 concentrations (0.1 M, 1.0 M, 5.0 M). Subsequently, the introduction of Strontium (Sr-85) and Europium (Eu-152) stock solutions was carried out to simulate the presence of fission products typically contented in the spent nuclear fuel. When the operation proceeds, the complex structure takes the following form. 􀜷􀜱􀬶 􀬶􀬾(􀜽􀝍) + 2􀜰􀜱􀬷 􀬿(􀜽􀝍) + 2􀜶􀜤􀜲(􀝋􀝎􀝃) ↔ 􀜷􀜱􀬶(􀜰􀜱􀬷)􀬶 ∙ 2􀜶􀜤􀜲(􀝋􀝎􀝃) Subsequently, separate samples were gathered from both the organic and aqueous phases for the quantification of gamma-rays and alpha particles. Alpha particle measurements were conducted utilizing the Liquid Scintillation Counter (LSC) system, while gamma-ray measurements were carried out using the High-Purity Germanium Detector (HPGe). The distribution ratio for U, Eu (Eu-152), and Sr (Sr-84) was ascertained by quantifying their activity through LSC and HPGe. Through the experiments conducted within this program, we have gained a comprehensive understanding of the selective solvent extraction of actinides. Specifically, uranium has been effectively separated from the aqueous phase into the organic phase using a combination of tributyl phosphate (TBP) and dodecane. Subsequently, samples containing U(VI), Eu(III), and Sr(II) underwent thorough analysis utilizing LSC and HPGe detectors. Our radiation measurements have firmly established that the concentration of nitric acid enhances the selective separation of uranium within the process.

SMR, which has recently been in the spotlight, has several advantages. However, it poses additional challenges in the areas of new design, digitalization, security, safety and safeguards. Among them, security refers to measures to protect nuclear materials and facilities from unauthorized access, theft, or destruction. Safeguards refer to measures to prevent the spread of nuclear weapons. The relationship between security and safeguards is complex and constantly evolving. In general, security measures are designed to protect nuclear materials and facilities from physical attack, while safeguards are designed to track and monitor the movement of nuclear materials and prevent them from being used to create nuclear weapons. In some areas security and safeguards work in complementary ways, and in other areas they conflict. But ultimately, finding a balance is what is effective and efficient. In conclusion, although the security and safeguards of SMRs have different key objectives, they are closely related and must be implemented comprehensively and consistently to ensure the safety of nuclear facilities, the public, and the environment. In this paper, we investigate how the safety and safeguards of SMR are currently being researched and analyze what difficulties there are when assuming that they are operated as a single interface.

Owing to the great demand for portable and wearable chemical sensors, the development of all-solid-state potentiometric ion sensors is highly desirable considering their simplicity and stability. However, most ion sensors are challenged by the penetration of water and gas molecules into ion-selective membranes, causing unstable and undesirable sensing performances. In this study, a hydrophobic ionic liquid-modified graphene (Gr) sheet was prepared using a fluid dynamics-induced exfoliation and functionalization process. The high hydrophobicity and electrical double-layer capacitance of Gr make it a potential solid-state ion-to-electron transducer for the development of potentiometric sodium-ion ( Na+) sensors. The as-prepared Na+ sensors effectively prevented the formation of the water layer and penetration of gas species, resulting in stable and high sensing performances. The Na+ sensors showed a Nernstian sensitivity of 58.11 mV/[Na+] with a low relative standard deviation (0.46), fast response time (5.1 s), good selectivity (K < 10− 4), and good durability. Furthermore, the Na+ sensor demonstrated its feasibility in practical applications by measuring accurate and reliable ion concentrations of artificial human sweat and tear samples, comparable to a commercial ion meter.

Bee pollen is a valuable apitherapeutic product and has been known to have diverse biological activities, including antimicrobial, anti-inflammatory, and even anticancer activity. However, its effect on the immune system is not well studied and is rather controversial. This study intended to elucidate the biological activity of bee pollen on immunity. For this purpose, we used lyophilized bee pollen after wet grinding, which shows increased extraction of bioactive components and enhanced biological activity. First, lyophilized bee pollen after wet grinding significantly increased the proliferation of splenocytes isolated from normal mice. On the other hand, lyophilized bee pollen after wet grinding dose-dependently reversed splenocyte proliferation by concanavalin A or lipopolysaccharide. To clarify the activity of bee pollen on immunity lyophilized bee pollen after wet grinding was administered daily to mice for five weeks and isolated splenocytes. In this study, there was no significant difference in the population of immune cells and the size of spleen between bee pollen- and sterile water-treated groups. However, proliferation of splenocyte isolated from bee pollen-administered animals was boosted by both concanavalin A and lipopolysaccharide. Finally, kaempferol, a well-known flavonoid from bee pollen, dose-dependently increased splenocyte proliferation by both Con A and LPS. On the other hand, naringenin, another flavonoid in the bee pollen, dose-dependently inhibited the proliferation of splenocytes by Con A and LPS. Together, these data indicate that bee pollen may be able to prime the immunity to boost immune reaction after inflammation.

The effect of the surrounding vegetation on the seed germination and growth of mountain-cultivated ginseng (MCG, Panax ginseng C.A. Meyer) was investigated. Seed germination rate and growth were tested for allelopathy effects on four forest tree species after treatment with fallen leaves and leaf extracts. In the case of soil treatment through fallen leaves and crushed leaves, the germination rate was lower in the Quercus myrsinifolia treatments, and the average germination time was slower when Chamaecyparis obtusa was treated. In the case of Pinus densiflora and Quercus variabilis, which are used in most of the MCG cultivation areas, they did not have a significant effect on seed germination. In the fallen leaves treatments, the stem showed a tendency to lengthen. The hot water extract treatment showed a higher germination percentage than the cold water extract treatment. The extract treatment showed a deficient germination percentage of some MCG seeds. However, in the case of the treatments except for this, the germination percentage was similar to that of the control treatment. However, the Mean Germination Time, germination rate, and germination value were faster and higher than the control treatment. As a result of calculating the allelopathic index (AI) of MCG according to the extract treatment of 4 species, most had a negative effect on germination, and P. densiflora and Q. variabilis extracts showed the most significant effect. The ginsenoside content was higher in the fallen leaves treatment than in the control. The above results will help select and manage MCG plantations.

기후변화와 세계시장 개방에 따른 외래 및 돌발해충의 종류는 다양해지고 밀도는 지속적으로 증가하고 있지 만 발생 실태에 관한 자료는 미흡하다. 본 연구는 경남지역 돌발 및 남방계 해충의 발생과 피해조사를 위해 미국선 녀벌레, 썩덩나무노린재, 담배거세미나방 등 3종을 경남 18시·군에서 조사하였다. 미국선녀벌레는 약충기(6월), 성충기(9월) 조사를 진행하였고, 길이가 50cm 이상되는 가지의 밑동에서 위쪽으로 50cm 내 개체를 육안조사하 였다. 썩덩나무노린재는 콩 개화기(7월), 등숙기(9월) 조사를 진행하였고 지점당 집합페로몬 트랩 1개를 설치하 고 1주 후 채집된 마리 수를 조사하였다. 담배거세미나방은 성페로몬 트랩 1개를 설치한 뒤 1주 후 채집된 마리 수를 조사하였다. 미국선녀벌레는 의령, 함안, 함양 등에서 발생이 많았고, 전년대비 발생이 소폭 감소하였다. 썩덩나무노린재는 합천, 밀양, 함양 등에서 발생이 많았고, 담배거세미나방은 전시군에서 발생이 확인되었으 며, 특히 함양, 산청, 사천, 고성 등에서 밀도가 높았다.

최근 기후변화에 따라 아열대 작물 재배가 증가하면서 경남지역 망고 재배면적도 크게 증가하고 있다. 하지만 망고에 발생하는 병해충 발생 정보가 부족하여 2022년부터 현재까지 경남지역에 있는 망고농장을 조사하였으 며, 그 결과 병해 6종, 해충 8종 발생을 확인하였다. 특히 경남지역 망고 포장에서 꽃노랑총채벌레, 대만총채벌레, 볼록총채벌레 등의 발생을 확인하였고, 통영, 함안, 밀양 등에서 총채벌레류에 의한 피해가 발생하였다. 많은 농가에서 총채벌레류 방제를 위해 화학농약에 의존하고 있으나 총채벌레는 반복적인 약제 노출시 빠른 세대 진전으로 인해 저항성 발달이 쉽기때문에 방제에 어려움을 겪고 있다. 이러한 문제를 해결하고자 색상별 끈끈이 트랩의 총채벌레류 유인효과를 확인하였으며, 꽃노랑총채벌레는 노랑, 주황, 연두, 대만총채벌레는 빨강, 노랑, 파랑, 볼록총채벌레는 파랑, 노랑, 빨강 순으로 유인효과가 높은 것을 확인하였다.

오리엔탈과실파리(Bactrocera dorsalis)는 형태학적, 생태학적으로 습성이 유사한 70여종을 포함하여 Bactrocera dorsalis species complex (오리엔탈과실파리종군)에 포함되어 있다. 이 종은 동남아시아와 태평양 일대에 널리 분포하며 기주범위가 넓은 다식성 해충으로 가장 많이 연구된 분류군 중 하나이다. 이 종은 여러 나라에서 검역병해충으로 지정되어 있으며, 우리나라에서는 유입될 경우 감귤류 및 여러 농작물에 심각한 피해 를 줄 수 있어 금지병해충으로 지정하여 관리하고 있는 종이다. 우리는 이 종과 가장 유사한 4종(B. carambolae, B. correcta, B. latifrons, B. verbascifoliae)과 비교하여 형태학적 연구를 수행하였다. 본 연구에서는 각 종별 특징 및 진단형질을 제공하고, 도판을 이용하여 형태적 차이를 제시하였다.

등에모기과(Ceratopogonidae)는 파리목(Diaptera)에 속하는 미소곤충이다. 이 중 사람과 반추류를 포함하는 척추동물을 흡혈하는 점등에모기속(Genus Culicoides)은 세계적으로 1,368종 이상이 보고되었으며 블루텅, 아프 리카 마역 등 60여개 이상의 질병을 매개하는 것으로 알려져 있다. 현재 국내에 서식하는 Culicoides는 37종이 보고되어있으며, 아카바네, 츄찬 등의 질병을 매개한 기록이 있다. 이에 기후변화에 따른 개체 발생양상과 분포 를 조사하고자 본 연구에서는 아열대화 및 해외유입을 고려하여 경상남도, 전라남도, 제주도 세 권역의 축사 15개 지역에서 5월부터 8월까지 유문등을 이용하여 채집하였다. 총 19종 103,365개체가 채집되었고 Culicoides arakaawae(83,922), Culicoides punctatus(11,184), Culicoides tainanus(3,298) 3종이 전체 채집량 중 95.2%를 차지하 였다. 각 샘플을 채집시기별, 종별, 지역별로 정리한 결과, 종다양성이 가장 높은 지역은 13종이 채집된 진주, 가장 낮은 곳은 3종이 채집된 제주5 지점이었다. 보관된 샘플은 유전자원 확보 및 바이러스보유검사 등의 추가실 험을 통해 국내 등에모기 연구를 위한 기초자료로 활용될 수 있을 것으로 기대된다.

Culex pipiens complex는 West Nile virus의 주요 매개체이며, 대한민국에는 Cx. pipiens pallens와 Cx. pipiens f. molestus가 서식한다고 알려져 있다. 그러나 현재까지 대한민국에서 진행된 Culex pipiens complex의 살충제 관련 실험은 종 수준 이하의 단계에서 비교가 이루어지지 않고 있다. 이에 본 연구에서는 대한민국의 13개 지역에 서 Culex pipiens complex를 채집하였고, 분자 마커를 이용해 종 수준 이하 단계까지 분류를 진행한 뒤 각 분류군의 Acetylcholinesterase-1(Ace-1)와 Voltage-gated sodium channel(Vgsc) 유전자에 대한 저항성 돌연변이 존재 유무를 확인하였다. Ace-1 영역 확인 결과, Cx. pipiens f. molestus에서는 저항성이 확인되지 않았으며, 목포에서 채집된 Cx. pipiens pallens 1개체에서 저항성 개체가 발견되었다. Vgsc 영역에서는 저항성 유전형질을 보유한 개체가 Cx. pipiens pallens와 Cx. pipiens f. molestus에서 모두 발견되었으며, 다양한 지역에서 서로 다른 비율로 존재하는 것을 확인하였다. 본 조사 결과는 향후 대한민국에 서식하는 Culex pipiens complex의 효율적인 방제를 위한 기초자료로 활용될 수 있을 것이다.

양봉꿀벌은 한 마리 여왕벌을 중심으로 일벌 및 수벌들이 군집을 이루고 있는 사회성 곤충이다. 꿀벌은 여왕벌 이 깨어나면 처녀비행 (반경 2.4~7.4km )을 하여 공중에서 여러 마리의 수벌들과 교미를 한 후, 자신의 봉군 내부로 돌아와 평생을 살아가는 생태적 특성을 가지고 있다. 이와 같은 이유로 계통 증식 또는 품종 육종에서 외부의 오염원을 차단하기 위해서는 여왕벌과 수벌이 격리된 지역에서 교미가 이루어져야 한다. 본 연구는 여왕벌과 수벌이 격리될 수 있는 국내 도서지역을 중심으로 격리교미 연구를 2020년부터 2023년 봄부터 가을까지 수행하 였으며, 육종을 위한 격리교미의 효율성을 분석하고자 하였다. 도서지역은 전남 - 낙월도, 전북 - 위도, 왕등도, 식도에서 수행되었으며, 섬 크기, 경관 환경 요인, 교미 시기 등에 의해 격리교미의 성공률이 어떻게 변하는지를 확인하였다.

우리나라 식물방역법은 검역병해충으로부터 국내 농업 및 자연환경을 보호하고자 규제병해충(검역병해충, 잠정규제병해충, 규제비검역병해충) 관련 위험평가, 식물검역기술개발계획, 식물검역 절차 및 방법, 검역결과 에 따른 처분, 규제병해충 예찰 및 방제 등에 관한 다양한 법적 절차 등을 규정하고 있다. 하지만, 식물검역병해충 을 어떻게 취급하여야 할 지에 관한 내용은 없다. 따라서 식물방역법이 추구하는 목적을 달성하기 위하여서는 ① 검역병해충을 어떻게 취급하여야 할 지를 규정하여야 하며, ② 검역병해충을 취급하는 시설(검사, 연구, 운송, 보관 등) 기준을 설정하고, ③ 검역병해충 취급 시설을 인증하고, 주기적인 재인증 기준을 설정하여야 한다. 이를 위하여 먼저 식물방역법에 검역병해충 취급시설 등에 관한 규정을 신설하고, 시행령, 시행규칙에 반영한 후에 ① 검역병해충 취급요령 ② 검역병해충 취급시설 기준 ③ 검역병해충 취급시설 인증기준 등의 고시를 제정하여 야 한다. 이를 위하여 식물병해충 관련 학계의 의견 반영이 가장 중요하다.