Early in the growing season of 1976, rain and cool weather favored the blighting of leaves of young plants of barley by Fusarium nivale. The fungus was recovered in culture from infected foliage, and the perithecia of Calonectria nivalis were demonstrated to be present as well as the Fusarium state. On 22 April 1976, in Suweon, plants pulled at random revealed stem lesions from which F. nivale was cultured. On S May 1976 near Kwangju. Perithecia were found embedded within leaf sheaths and blades of mature wheat and barley plants. It was evident in the 1976, 1977 season that Fusarium(Calonectria) nivale was common but unrecognized as an early season pathogen of barley in Korea. The probable source of primary inoculum was the infected refuse from the previous season's barlry and wheat crops. Stem lesions caused by this fungus were considered to he detrimental to the maximum yield of barley or wheat,

초 록 본 실험은 Corynebacterium속 식물병원세균에 관한 연구의 일환으로서 Corynebacterium속 식물병원세균의 종 및 속으로서의 특성을 구명하기 위하여 행하여진 것으로서 균체구성단백의 정량은 Lang의 Messier 변법을 사용하였으며 균채 구성단백의 아미노산정량은 미생물 정량에 의하였다. Corynebacterium 속 식물병원세균은 타속의 병원세균에 비하여 다소 적은양의 균체 구성단백을 가지고 있었으며 균체구성단백의 아미노산, Cystein, Trypthophane, Histidine, Phenylalanine 및 Isoleucin에 있어서도 같은 결과를 나타내었다. 허나 이 현상은 종적 혹은 개체의 균주의 특성으로서 분류에는 관계를 갖지 않고 있음이 밝혀졌다

본 실험은 Corynebacterium속 식물병원세균에 관한 연구의 일환으로서 Corynebacterium속 식물병원세균의 종 및 속으로서의 특성을 구명함과 동시에 C. sepedonicum이 생성하는 Rumiflabin에 기초를 둔 ultraviolet method의 재검토를 위하여 행하여 진 것으로 vitamin B군의 정량은 미생물 정량에 의하였다. 대다수의 식물병원세균은 Thiamine (vitamin ), Nicotinic acid, Biotin 및 안식향산을 생장물질로서 사용하였다. Riboflavin은 corynebacterium속 식물 병원세균 (C. rathay 및 C. fascians는 제외)은 물론 타속의 식문병원세균도 생성하는 점으로 Corynebacterium속 식물병원 세균의 특성이 아니라는 점이 구명되었으며 sepedonicum에 의하여 발생되는 감자의 윤부병과 청고병과의 감별에 사용되어온 Ultra-violet light법은 재검토되어야 한다.

Deep geological repositories (DGR) count amongst the world largest environmental protection projects. They are the internationally advocated reference solution for the long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF). Many countries have engaged in programs to develop their own DGR. In Europe, four countries have passed the important milestone of choosing or announcing the appropriate site for the location of their HLW disposal facilities. Finland has almost finished the commissioning of its DGR and should start industrial disposal operations in 2025. Sweden has authorized the construction of its DGR and is finalizing the licensing document to start construction. France is reviewing the construction license application of its DGR. Switzerland has proposed the location of its DGR and is carrying out the production of the documentation for the license application. These four countries took decades to choose the location for their DGR. The length of this process is explained by 1) the amount of technical investigations and studies that were carried out to first identify, select and then fully characterize the suitable site and 2) the progressive decision-making process defined by their respective legal frameworks, including the participation and engagement of communities and stakeholders.

A procedure for minimizing the environmental burden and maximizing the efficiency of storage sites used for the final disposal of spent fuel has been proposed. In this procedure, fission products (highly mobile and producing heat) are collected, and uranium and TRU-RE (transuranium-rare earth) oxide are independently stored. The possibility and applicability of radiation measurement for monitoring the nuclear materials effectively throughout the process has been simulated and evaluated. For the simulation, the properties of the chemical processes were analyzed, the major radiation emitters were determined, and the production of nuclear materials by chemical reactions were evaluated. In each process, the content of nuclear material was changed by up to 20% to represent abnormal conditions. The results showed that the plutonium peak was matched with the change in the TRU content and the measured signal was changed linearly with respect to the content change of the plutonium. From the neutron measurement, a linear response of the TRU content variation was obtained. In addition, a logic diagram was developed for the nuclear monitoring. The integration of radiation detections is recommended for monitoring the process effectively and efficiently.

Because most spent nuclear fuel storage casks have been designed for low burnup fuel, a safety-significant high burnup dry storage cask must be developed for nuclear facilities in Korea to store the increasing high burnup and damaged fuels. More than 20% of fuels generated by PWRs comprise high burnup fuels. This study conducted a structural safety evaluation of the preliminary designs for a high burnup storage cask with 21 spent nuclear fuels and evaluated feasible loading conditions under normal, off-normal, and accident conditions. Two types of metal and concrete storage casks were used in the evaluation. Structural integrity was assessed by comparing load combinations and stress intensity limits under each condition. Evaluation results showed that the storage cask had secured structural integrity as it satisfied the stress intensity limit under normal, off-normal, and accident conditions. These results can be used as baseline data for the detailed design of high burnup storage casks.