흰불나방의 휴면용과 비휴면용에서 탄수화물 함량을 비교하였다. 1. 저온상태()에 보관한 휴면용은 실온에 둔 것 보다 글리코겐(glycogen)함량은 적었지만 트레할로스(trehalose)와 솔비톨(sorbitol)의 양은 많았다. 2. 휴면용에서 혈액의 삼투압은 비휴면용의 것 보다 높게 나타났다. 3. 휴면용의 평균 산소 소비량은 비휴면용 보다 배 적었다.

초지조성용 2종복합비료를 개발코자 시제품(N-P2O5-K2O-MgO-B2O3 : 8-25-7-3-0.2)을 일반단비와 공시하여 비효를 비교검사하였다. 겉뿌림 배양초지(orchardgrass, tall fescue, kentucky bluegrass 및 ladino clover)에서 2년간 수행하였으며 1보에서는 토양의 화학성 및 목장의 초기생육상, 본고에서는 수량성, 식생구성비율 및 목장의 영양성분에 미치는 영향을 검사한 결과는 다음과 같다

본(本) 시험(試驗)은 2차천이(次遷移) 식생(植生)의 Carex ferruginea 군락(群落)인 독일(獨逸)의 남부지방인(南部地方)에 위치(位置)한 Bavarian Alps 지역(地域)에서 PK-시비(施肥) 및 면양(緬羊) 방목(放牧)에 의(依)한 식물군락(植物群落)의 천이(遷移)를 조사(調査)코자 수행(遂行)되었다. 1. Carex ferruginea 군락(群落)은 처리(處理)(환경(環境)) 조건(條件)에 의(依)해 변화(變化)되었는데 면양방목(緬

호맥(胡麥)의 생육시기별(生育時期別) 생초(生草) 및 건물소화율(乾物消化率)과 부위별(部位別) 생산량(生産量) 및 이들 시기별(時期別)로 일반성분(一般成分)과 생산량(生産量)을 비교(比較)하기 위하여 수잉기(穗孕期), 출수기(出穗期), 유숙기(乳熟期), 호숙기(糊熟期) 및 황숙기(黃熟期)의 5단계로 나누어 실시(實施)한 시험결과(試驗結果)를 요약(要約)하면 다음과 같다. 1. 생육시기별(生育時期別) 생초수량(生草收量)은 호숙기(糊熟期)가 가장 많았으며(

AOM and lamp tests were carried out with soybean, corn, palm oil and beef tallow without the addition of antioxidant. The evaluation of rancidity for the stability was determined by changes of peroxide value and acid value, and the correlation between the stability and the composition of fats and oils was examined. The results obtained were as follows. 1. In the AOM test, POV began to rise in the order of corn oil, soybean oil, beef tallow and palm oil. However, the time required to reach POV 100 in beef tallow was faster than other fats and oils. It was found that there was a good correlation between POV and content of tocophrol. 2. In the lamp test by light of main wavelength 253.7nm, beef tallow was stabler than soybean and corn oil. It was because the absorption of light into beef tallow was much smaller than others, since beef tallow was fats. Palm oil was very stable in all the samples during AOM and lamp test.

Our country has been produced much amounts of panax ginseng roots which has a stimulating effects on the metabolism of protein, lipid and nucleic acids in the body. And the leaf trunk of panax ginseng were also produced a considerable amounts as the by - products. Therefore, this study was devised to observe the nutritional effect to rats feeding of rice diet supplemented with by - products of panax ginseng, male Albino rats of pure strain weighing 73.8 ± 0.7 g were used as experimental animal to investigate the changes of cholesterol in heart and testis. The animals were divided into sixteen diet group, they were the protein contents of 9%, 12%, 15% and 18% supplemented with 2% panax ginseng roots and its by - products respectively. The group without the supplements were used as the control. The diet group were again divided into 2 groups according to the feeding terms, 4 weeks and 8 weeks. It is concluded that the free from cholesterol and total cholesterol contents in the heart and testis with the supplements of panax ginseng roots and its by - products showed significant difference compared to the control group.

Cercospora kikuchii에 의해서 발병된 대두종자의 부패균에 대한 획득저항성기작을 구명코자 본 연구를 실시하였다. 1. 대두의 건전종자, 자연열개종자, 인위적 상처종자 및 자반병 감염종자재의 전단백질 함량에는 차이가 없었으나 peroxidase활성도는 감염종자에서 월등히 높았다. 2. 대두의 건전종자와 자반병 감염종자의 종피 및 자엽내의 단백질함량에는 큰 차이가 없었으며 peroxidase활성도는 자엽에서는 차이 가 없었으나 종피에서 건전한 종피보다 자반병에 감염된 종자가 2.5배 정도 높은 활성도를 보였다. 3. Polyphenol oxidase는 대두의 건전종자의 자반병 감염종자 모두 활성도가 너무 낮아 측정할 수 없었다. 4. 전기영동에 의한 peroxidase isozyme pattern은 건전종자와 감염종자간에 차이가 없었다. 5. 자반병에 대한 저항성기작은 자반병균에 의하여 대주종피 자체내에서 생화학적 방어기작이 더욱 활성화 하였으며 peroxidase활성도의 증가는 병원균에 대한 반응으로 사료된다.

This paper concerns the receding of the eastern coastline of Korean peninsula at a macroscopic point of view, the result is as following. 1. Eastern coast is gradually developed from maturity stage to full maturity stage. 2. The coastline recession due to sea level rise is amounted to the receding distance, x=0.045 m per yr. 3. The author proposes another classification from the new view point, which is classified by comparing quantities between river supplying sediment loads, and the littoral drifting due to wave actions. According this, eastern coast is receding(Type Q-A), and we could find it's geomorphological characteristics. 4. The general piofile of eastern coast sand beach is erosional storm profile(Type I) which accompany offshore bar. 5. From the wave measuring data of eastern coast(Hoopo port), I can derive the linear regression line of the exceedance probability of wave height from the log-normal distribution. z=O. 113+4.335 loglo H, r=0.983. Above equation made it possible to estimate Ω[=P(H>Hc)]for the effective wave height Hc=2. Om4, 4. Om and their corresponding values are considerable (7.8%, 0.3%) 6. Eastern coastline certainly have the tendency of erosive and receding, owing to the sea level rise, poor sediment source and effective wave actions. It's very desirable to survey coastline evolution for a long time systematically, in order to make more elaborate diagnosis.

초 록 우리나라에 분포하고 있는 벼 도열병균의 생리형(레이스)의 분화 및 지역적분포와 년차적 변동을 알아보기 위하여 1962년부터 1971년까지 전국에서 채집분리한 1044개균주를 류별한 결과 T-레이스군이 4, C-레이스군이 15, N-레이스군 8, 모두 27개의 레이스가 유별되었다. 한국재래 및 장려품종과 일본형품종들이 주로 재배됐던 1966년이전에는 N-레이스군이 로 지배적이었으나 그이후 중국계통 및 통일품종의 재배면적이 늘어남에 따라 T레이스군이 , C레이스군이 로 증가하는 경향을 보였다. 1966년이전에는 T.C레이스가 수원지방을 중시으로 조금씩 발생하는 경향을 보였으나 그이후 점차 전국적으로 널리퍼져 지역적인 분포차를 인정할 수 없었다. 지금까지 우점레이스군으로는 N-2, C-8레이스가 널리 분포되어 왔고 특히 1970년이후 인도형과 재래품종과의 교잡종인 통일의 확대재배로 새로운 레이스(T-d 레이스)가 1973년부터 출현하여 지금까지 저항성을 보였던 Tetep이 이병성으로 나타나고 있어 앞으로 레이스의 추이와 통일계통등의 인도형 수도를 침해하는 새로운 레이스의 분화에 대한 연구 및 그에 대한 적절한 대책이 강구되어야 하겠다.

The concept of deep geological disposal for high-level radioactive waste is based on an engineered barrier system (EBS), including a canister, bentonite buffer and backfill material. The bentonite buffer is key component of the EBS to prevent groundwater infiltration and radionuclide leakage. However, the bentonite buffer can become saturated due to groundwater flow through the excavation damaged zone in the adjacent rock, causing erosion of bentonite buffer and affecting the long-term performance of EBS. While the RH (relative humidity) sensor is commonly used to assess the degree of saturation in the bentonite buffer, it has a critical challenge due to its sensor size, which can disturb the overall integrity of the bentonite buffer during the initial installation process. In contrasts, the electrical resistivity test, widely known as a non-destructive method, is used to predict soil properties such as the degree of saturation and water contents. This method measures the electric resistance of materials using electric current induced by electric potential difference between two electrodes. Notably, there is no study that assess the integrity of bentonite buffer in a nuclear waste repository using electrical resistivity measurement. This study presents the electrical resistance numerical module under steady state using commercial finite element method (FEM), and quantitatively estimate the change of electrical resistance according to saturation and erosion of bentonite buffer. Furthermore, the electric potential and current density distribution formed between two electrodes are analyzed.

The radionuclide management process is a conditioning technology to reduce the burden of spent fuel management, and refers to a process that can separate and recover radionuclides having similar properties from spent fuels. In particular, through the radionuclide management process, high heat- emitting, high mobility, and high toxicity radionuclides, which have a significant impact on the performance of disposal system, are separated and managed. The performance of disposal system is closely related to properties (decay heat and radioactivity) of radioactive wastes from the radionuclide management process, and the properties are directly linked to the radionuclide separation ratio that determines the composition of radionuclides in waste flow. The Korea Atomic Energy Research Institute have derived process flow diagrams for six candidates for the radionuclide management process, weighing on feasibility among various process options that can be considered. In addition, the GoldSim model has been established to calculate the mass and properties of waste from each unit process of the radionuclides management process and to observe their time variations. In this study, the candidates for the radionuclide management process are evaluated based on the waste mass and properties by using the GoldSim model, and sensitivity analysis changing the separation ratio are performed. And the effect of changes in the separation ratio for highly sensitive radionuclides on waste management strategy is analyzed. In particular, the separation ratio for high heat-emitting radionuclides determines the period of long-term decay storage.

Change in chemical constitution of a zirconium sample treated at the simulated condition of a pressurized water reactor (water at 315°C and 15.5 MPa) was investigated using X-ray diffraction (XRD) and Raman spectroscopy. We observed swelling of the zirconium sample as well as the change in its color from silver to gray treated after the pressurized water at high temperature. On the basis of XRD and Raman data, we confirmed that the variation in composition of zirconium specimen from hexagonal Zr to monoclinic ZrO2 occurred at the simulated PWR condition. Therefore, we suggested that the oxidation of zirconium appeared due to the reaction with water at high temperature and pressure, as shown in the following reaction: Zr + 2H2O → ZrO2 + 2H2.

In Korea, borated stainless steel (BSS) is used as a storage rack in spent fuel pools (SFP) to maintain the nuclear criticality of spent fuels. As the number of nuclear power plants and the corresponding amount of spent fuels increased, the density in SFP storage rack also increased. In this regard, maintaining subcriticality of spent nuclear fuels became an issue and BSS was selected as the structural material and neutron absorber for high density storage rack. Since it is difficult to replace the storage rack, corrosion resistance and neutron absorbency are required for long period. BSS is based on stainless steel 304 and is specified in the ASTM A887-89 standard depending on the boron concentration from 304B (0.20-0.29% B) to 304B7 (1.75-2.25% B). Due to the low solubility of boron in austenitic stainless steel, metallic borides such as (Fe, Cr) 2B are formed as a secondary phase. Metallic borides could cause Cr depletion near it, which could decrease the corrosion resistance of the material. In this paper, the long-term corrosion behavior of BSS and its oxide microstructures are investigated through accelerated corrosion experiment in simulated SFP conditions. Because the corrosion rate of austenitic stainless steel is known to be dependent on the Arrhenius equation, a function of temperature, the corrosion experiment is conducted by increasing the experimental temperature. Detail microstructural analysis is conducted using a scanning electron microscope, transmission electron microscope and energy dispersive spectrometer. After oxidation, a hematite structure oxide film is formed, and pitting corrosion occurs on the surface of specimens. Most of the pitting corrosion is found at the substrate surface because the corrosion resistance of the substrate, which has low Cr content, is relatively low. Also, the oxidation reaction of B in the secondary phase has the lowest Gibbs free energy compared to other elements. Furthermore, oxidation of Cr has low Gibbs free energy, which means that oxidation of B and Cr could be faster than other elements. Thus, the long-term corrosion might affect the boron content and the neutron absorption ability of the material. Using boron’s high cross-section for neutrons, the neutron absorption performance of BSS was evaluated through neutron transmission tests. The effect of the corrosion behavior of BSS on its neutron absorption performance was investigated. Samples simulated to undergo up to 60 years of degradation before corrosion through accelerated corrosion testing did not show significant changes in the neutron shielding ability before and after corrosion. This can be explained in relation to the corrosion behavior of BSS. Boron was only leached out from the secondary phase exposed on the surface, and this oxidized secondary phase corresponds to about 0.17% of the volume of the total secondary phase. This can be seen as a very small proportion compared to the total boron content and is not expected to have a significant impact on neutron absorption performance.

Korea Atomic Energy Research Institute is developing a radionuclide management processes as a conditioning technology to reduce the burden of spent fuel disposal. The radionuclide management process refers to a process managing radionuclides with similar properties by introducing various technology options that can separate and recover radionuclides from spent fuels. In particular, it is a process aimed at increasing disposal efficiency by managing high-heat, high-mobility, and high-toxic radionuclides that can greatly affect the performance of the disposal system. Since the radionuclide management process seeks to consider various technology options for each unit process, it may have several process flows rather than have a single process flow. Describing the various process flows as a single flow network model is called the superstructure model. In this study, we intend to develop a superstructure model for the radionuclide management process and use it as a model to select the optimal process flow. To find the optimal process flow, an objective function must be defined, and at the fuel cycle system level multiple objectives such as effectiveness (disposal area), safety (explosure dose), and economics (cost) can be considered. Before performing the system-level optimization, it is necessary to select candidates of process flow in consideration of waste properties and process efficiency at the process level. In this study, a sensitivity analysis is conducted to analyze changes in waste properties such as decay heat and radioactivity when the separation ratio varies due to the performance change for each unit process of the radionuclide management process. Through this analysis, it is possible to derive a performance range that can have waste properties suitable for following waste treatment, especially waste form manufacturing. It is also possible to analyze the effect of waste properties that vary according to the performance change on waste storage and management approaches.