본 연구는 환경교육용 보드게임 개발에 관한 연구다. 이를 위해 문헌 고찰과 전문가 인터뷰를 실시하여 핵심 메커니즘과 용어를 도출하였다. 또한, 타당도와 신뢰도 검증을 위하여 델파이 조사를 진행하였다. 연구 결과 9개 항목에 대하여 합의가 이뤄졌으며, 이를 기반으로 ‘수풀로 메이커’ 프로토타입을 제작하고 플레이테스트 를 진행하였다. 그 결과, 환경에 대한 관심, 생태복원의 개념, 탄소 중립에 대한 이해를 보여, 연구의 초기 목 적을 달성한 것으로 나타났다. 본 연구로 인해 개발된‘수풀로 메이커’는 아동과 청소년의 환경교육 교재의 역할 뿐만 아니라, 환경에 대한 깊이 있는 이해를 견인하고, 더 나아가 실천양식 변화의 잠재성을 키우는 역 할에 기여할 수 있을 것으로 기대한다.

Kori Unit 1 nuclear power plant is a pressurized water reactor type with an output of 587 Mwe, which was permanently shut down on June 18, 2017. Currently, the final decommissioning plan (FDP) has been submitted and review is in progress. Once the FDP is approved, it is expected that dismantling will begin with the secondary system, and dismantling work on the primary system of Kori Unit 1 will begin after the spent nuclear fuel is taken out. It is expected that the space where the secondary system has been dismantled can be used as a temporary storage place, and the entire dismantling schedule is expected to proceed without delay. The main equipment of the secondary system is large and heavy. The rotating parts is connected to a single axis with a length of about 40 meters, and is complexly installed over three floors, making accessibility very difficult. A large pipe several kilometers long that supplies various fluids to the secondary system is installed hanging from the ceiling using a hanger between the main devices, and the outer diameter of the pipe is wrapped with insulation material to keep warm. In nuclear secondary system decommissioning, it is very important to check for radiation contamination, establish and implement countermeasures, and predict and manage safety and environmental risks that may occur when cutting and dismantling large heavy objects. So we plan to evaluate the radiation contamination characteristics of the secondary system using ISOCS (In- Situ Object Counting System) to check for possible radioactive contamination. According to the characteristics results, decommissioning plans and methods for safe dismantling by workers were studied. In addition, we conducted research on how to safely dismantle the secondary system in terms of industrial safety, such as asbestos, cutting and handling of heavy materials and so on. This study proposes a safe decommissioning method for various risks that may occur when dismantling the secondary system of Kori Unit 1 nuclear power plant.

Structural stability of a waste form can be provided by the waste form itself (steel components, etc.), by processing the waste to a stable form (solidification, etc.), or by emplacing the waste in a container or structure that provides stability (HICs or engineered structure, etc.). The waste or container should be resistant to degradation caused by radiation effects. In accordance with the requirements for the domestic waste acceptance criteria, irradiation testing of solidified waste forms containing spent resin should be conducted on specimens exposed to a dose of 1.0E+6 Gy and other material 1.0E+7 Gy. Expected cumulative dose over 300 years is about 1.770E+6 Gy for spent resin and 0.770E+6 Gy for dried concentrated waste generated from NPPs generally. According to NRC Waste Form Technical Position, to ensure that spent resins will not undergo adverse degradation effects from radiation, resins should not be generated having loadings that will produce greater than 1E+6 Gy total accumulated dose. If it necessary to load resins higher than 1E+6 Gy, it should be demonstrated that the resin will not undergo radiation degradation at the proposed higher loading. This is the recommended maximum activity level for organic resins based on evidence that while a measurable amount of damage to the resin will occur at 1E+6 Gy, the amount of damage will have negligible effect on disposal site safety. Cementitious materials are not affected by gamma radiation to in excess of 1E+6 Gy. Therefore, for cement-stabilized waste forms, irradiation qualification testing need not be conducted unless the waste forms contain spent resins or other organic media or the expected cumulative dose on waste forms containing other materials is greater than 1E+7 Gy. Testing should be performed on specimens exposed to IE+6 Gy or the expected maximum dose greater than 1E+6 Gy for waste forms that contain ion exchange resins or other organic media or the expected maximum dose greater than 1E+7 Gy for other waste forms. This is suggestion as a review result that requirement for irradiation testing of solidified waste forms has something to be revise in detail and definitively.

Domestic NPPs had produced the paraffin-solidifying concentrate waste (PSCW) for nearly 20 years. At that time radioactive waste management policy of KHNP was to reduce the volume and to store safely in site. The PSCW has been identified not to meet the leaching index after introducing the treatment system. PSCW has to be treated to meet current waste acceptance criteria (WAC) for permanent disposal. PSCW consists of dried concentrate 75% and paraffin 25% of volume. When PSCW is separated into a dried concentrate and a paraffin by solubility, total volume separated is increased twice. Final disposal volume of dried concentrate can reach to several times when solidifying by cement even considering exemption. Application of polymer solidification technology is difficult because dried concentrate is hard to make form to pellet. When PSCW is packaged in High Integrity Container (HIC), volume of PSCW is equal to the volume before package. The packaging process of HIC is simple and is no necessary of large equipment. It is important to recognize that HIC was developed to replace solidification of waste. HIC has as design goal a minimum lifetime of 300 years under disposal environment. The HIC is designed to maintain its structural integrity over this period, to consider the corrosive and chemical effects of both the waste contents and the disposal environment, to have sufficient mechanical strength to withstand loads on the container and to be capable of meeting the requirements for a Type A transport Package. The Final waste form is required for facilitating handling and providing protection of personnel in relation to solidification, explosive decomposition, toxic gases, hazardous material, etc. Structural stability of final waste form is required also. Structural stability of the waste can be provided by the waste itself, solidifying or placing in HIC. Final waste form ensure that the waste does not structurally degrade and affect overall stability of the disposal site. The HIC package contained PSCW was reviewed from several points of view such as physicochemical, radiological and structural safety according to domestic WAC. The result of reviewing shows that it has not found any violation of WCP established for silo type disposal facility in Gyeongju city.

There are generally two kinds of spent filter; one is spent filter media for mainly gaseous purification such as HEPA filter, the other is spent filter cartridge for liquid purification such as CVCS BRS cartridge type filter. The spent filter cartridge from liquid purification system has been storing in special shielding space in auxiliary building in NPPs since the beginning of 2006 according to the long term storage strategy for decaying short lived radionuclide and gaining the time for selecting practical treatment technology before final packaging. The spent filter cartridges generated Kori-1 reactor vary in their sizes as in length from 913 mm to 290 mm and range in radiation level from several hundred mSv per hour to below mSv per hour . It is high time that the spent filter cartridge is treated and packaged because LILW repository in Wolsung area is operating and Kori-1 reactor is scheduled to decommission. The spent filter cartridge is one of the wet solid wastes required of solidification. It is difficult for the spent filter cartridge to solidify because of their shape, structure, physical and chemical characteristics in addition to having high radiation level. NSSC notice defines that solidification of wet solid wastes include that solid material such as spent filter is encapsulated with cement, etc. as a form of macro-encapsulation. The radioactive waste acceptance criteria describes that non-homogeneous waste having above 74,000 Bq/g such as spent filter, dry active waste should be encapsulated with qualified material. Homogeneous waste such as spent resin, sludge, concentrated waste (liquid waste evaporator bottoms), etc. should be solidified complied with requirements except that spent filter which is allowed to encapsulate. It is needed to guide to the practice of these two requirements for spent filter. The sampling and test method is different between homogeneous solidification waste form and spent filter cartridge encapsulation waste form. For example, how core sample can be taken and how void space can be measured among spent filter cartridge in encapsulation waste form. The technical evaluation report for spent filter cartridge polymer encapsulation by US NRC has been reviewed and the technical position of US NRC was identified. As a result of review, improvement fields of waste acceptance criteria for spent filters are pointed out, and the technical position of US NRC for spent filter cartridge solidification is summarized. The recommendation on improvement directions for spent filter cartridge encapsulation is suggested.

2021년 4월부터 8월에 제주시의 비닐하우스에서 재배되는 목이버섯에서 거저리 일종이 발견되었으며, 그를 동정한 결과 제주진주거저리 (Platydema takeii Nakane, 1956)로 확인되었다. 상업적으로 재배되는 버섯에 있어서 거저리 해충으로 인한 우리나라의 첫 번째 피해 사례이다. 여 기서는 이 해충의 피해 증상과 성충 및 유충의 진단형질을 제공하고자 한다.

프리지아 ‘Sunny Gold’는 농촌진흥청 국립원예특작과학원 에서 2010년 노랑색 반겹꽃 프리지아 육성계통 ‘036010’을 모본으로 진노란색 홑꽃 ‘Golden Flame’을 부본으로 교배하여 획득한 종자로부터 2011년 진노란색 겹꽃의 향기가 강한 프리지아 계통을 선발하여 품종화 하였다. 2011년부터 2016년까지 개화 생육특성검을 수행하였으며 핵심수요자의 기호도 평가를 통해 선발되어 2017년 ‘Sunny Gold’ 로 명명되었다. ‘Sunny Gold’는 RHS color chart YO17B의 노란색 겹꽃 프리지아 품종으로 화폭은 6.7cm로 대조품종 ‘Golden Flame’ 6.1cm에 비해 크고, 분지수는 6.5로 다수확성 품종이다. 초장이 101.9cm로 초세가 강하다. ‘Sunny Gold’의 소화수 및 소화장은 각각 13.0개, 9.3cm이며 개화소요일수는 137.7일이다. 이 품종의 절화수명은 약 9일이며 자구번식력은 5.3배로 대조 품종 ‘Golden Flame’ 4.3배에 비해 우수하다. 전자코를 이용한 PCA분석결과 PC1과 PC2는 각각 99.3%와 0.6%로 전체 변이량의 99.9%를 반영하고 있다. Rader plot 분석결과 총 6개 센서에서 모두 ‘Sunny Gold’의 센서값이 향기가 강한 상용품종 ‘Yvonne’의 값에 비해 높게 나타나 ‘Sunny Gold’의 향기가 더 강한 것으로 나타났다.

농촌진흥청 국립원예특작과학원에서는 2018년 오리엔탈-트럼펫(OT) 종간잡종나리 ‘Pink Bella’를 개발하였다. 2008년 연노란색 OT 종간잡종나리 ‘Valparadiso’와 붉은색의 오리엔탈나리 ‘Scalini’를 각각 모본과 부본으로 화주 절단 수분법과 주 두교배법으로 각 3화를 인공교배하였고, 교배 후 미숙한 3개의 꼬투리를 수확하여 배가 형성된 배주를 기내에서 배양하여 잡종을 획득한 후 재배하였다. 육묘한 배양묘로부터 2011년 분홍색의 OT 종간잡종 나리 ‘OTO-11-43’ 계통을 개체 선발하였다. 2012년부터 2017년까지 선발된 계통은 자구와 인편번식, 조직배양을 이용하여 번식 및 양구한 후 1, 2차 생육특성 검정을 실시하였다. 2018년 3차 생육특성검정 및 소비자 기호도 평가를 수행한 결과 화색 및 화형에 대한 기호도가 높은 분홍색(RHS, RP62C)의 조기개화성 절화용 OT 종간잡종 나리 ‘Pink Bella’를 육성하였다. 3배체의 OT 종간잡종 나리로 초장은 131.7cm로 초장신장성이 우수하였다. ‘Pink Bella’의 화폭은 18.6cm이며 대조품종 ‘Table Dance’의 18.4cm와 유사한 크기였으며, 내화피의 폭, 길이 역시 대조품종과 통계적인 차이가 없었다. ‘Pink Bella’의 개화기는 6월 15일로 대조품종 ‘Table Dance’의 6월 28일에 비교하여 개화기가 13일 단축된 것으로 나타났으며 통계적으로 유의하였다.

백색칼라(Zantedeschia aethiopica) 신품종 ‘Swan’은 국립원 예특작과학원에서 2017년에 육성하였다. ‘Swan’의 모본은 다화성인 ‘Childsiana’와 무름병에 강한 ‘Wedding March’를 부본으로 2004년에 교배하여 구근을 양성 후 2008년부터 2016년까지 생육 및 개화 특성, 균일성에 대하여 특성검정을 실시하였다. 2017년에 3차 특성검정을 실시하여 최종 선발한 후 직 무육성품종심의회에 상정하여 ‘Swan’으로 명명하였다. ‘Swan’ 의 생육 및 개화특성은 부본으로 사용된 ‘Wedding March’를 대조품종으로 조사하였다. 백색(RSH W155C)화색의 ‘Swan’ 은 화포의 길이와 폭이 각각 11.2cm와 10.3cm인 중형 품종이다. 주당 화수는 2.1개로 대조품종보다 2배 많으며 꽃대길이가 77.1cm로 대조품종(68.7cm)보다 길다. 개화소요일수는 65 일로 조기개화 품종이다. 절화수명은 17일(대조12일)로 길며, 무름병 중도저항성으로 구근증식량(13.3개/주)이 우수하고 소비자기호도가 높다. ‘Swan’ 품종은 2020년 4월 28일에 국립종 자원에 품종등록(등록번호 제8092호)되었다.