Among the test categories of the personal dosimetry performance test in Korea, the reference neutron radiation field used for the mixed neutron-photon radiation field is generated by a D2Omoderated 252Cf source. There are some differences depending on the standards, D2O-moderated 252Cf source consists of the 252Cf source surrounded by the D2O sphere with a diameter of 30 cm, covered with a Cd shell of thickness approximately 0.051 cm ~ 0.1 cm. In order to optimize the design of the D2O sphere and establish the neutron radiation field for the personal dosimetry performance test in Central Research Institute of KHNP, the neutron spectra have been simulated by MCNP 6.2 code by design conditions and evaluated dose conversion coefficients. In the consideration of neutron irradiation facility, the basic design structure was determined a D2O sphere with a diameter of covered with a Cd shell and a cylindrical well is in the middle of sphere. Neutron source transfer tube is inserted into this well-shaped structure and neutron source was withdrawn from the tube. And by changing the following design conditions in detail, the neutron spectra were evaluated; 1) the entire diameter of the D2O sphere (with or without the diameter of 7.5 cm of well-shaped structure) 2) the location of the neutron source (distance from D2O) 3) thickness of Cd shell 4) purity of D2O. As a source spectrum, the spectrum of bare- 252Cf recommended by ISO 8529-1 was adopted and spectra were tallied using F4 tally at a distance of 120 cm from the neutron source. Finally, the fluence to dose conversion coefficients were calculated using the simulated spectra. As a result of the evaluation, in case that an entire diameter of the D2O sphere with a diameter of the source tube is 37.5 cm, the fluence to dose conversion coefficient was evaluated to about 4.4% lower than an entire diameter of the D2O sphere is 30 cm. And in case that the distance between the D2O and the top of the neutron source was about 3.75 cm which is a radius of well-type structure, it was evaluated to about 1.4% larger than the distance was about 1 cm, and when the thickness of Cd was 0.1 cm, it was evaluated to 0.8% larger than when it was 0.051 cm. Finally, when the purity of D2O was 99.99%, it was evaluated 1.5% lower than when it was 99%. Except for the diameter of D2O sphere, the differences on the other conditions are acceptable considering the uncertainty of the simulation. Therefore, the design of D2O-moderated 252Cf source was determined by considering source integrity, economic perspectives, and dose conversion coefficient given in ISO 8529: a D2O sphere with an entire diameter of 37.5 cm, filled with above 99% purity of D2O, and covered with a cadmium thickness of 0.1 cm. The fluence to dose conversion efficient was evaluated as 110.10 pSv cm2 for ambient dose H*(10), 115.21 pSv cm2 for personal dose Hp(10) respectively.

Hydrogen isotopes (H, D, T) separation technologies have received great interest for treatments of tritiated liquid waste produced in Fukushima. In addition, the separated deuterium and tritium can be utilized in various industries such as semiconductors and nuclear fusion as expensive and rare resources. However, separating hydrogen isotopes in gas and liquid forms still requires energyintensive processes. To improve efficiency and performance of hydrogen isotope separation, we are developing water electrolysis, cryosorption, distillation, isotope exchange, and hydrophobic catalyst technologies. Furthermore, an analytical method is studied to evaluate the separation of hydrogen isotopes. This presentation introduces the current status of hydrogen isotope research in this research group.

In the design of a spent-fuel (SF) storage, the consideration of burnup credit brings the benefits in safety and economic views. According to it, various SF burnup measurement systems have been developed to estimate high fidelity burnup credit, such as FORK and SMOPY. Recently, there are a few attempts to localize the SF burnup measurement system in South Korea. For the localization of SF burnup measurement systems, it is very important to build the isotope inventory data base (DB) of various kinds of SFs. In this study, we performed DeCART2D/MASTER core follow calculations and McCARD single fuel assembly (FA) burnup analyses for Hanbit unit 3 and confirmed the characteristic of the isotope inventory over burnup. Firstly, the core follow calculations for Cycles 1~7 were performed using DeCART2D/MASTER code system. The core follow calculation is very realistic and practical because it considers the design conditions from its nuclear design report (NDR). Secondly, the Monte Carlo burnup analyses for single FAs were conducted by the McCARD Monte Carlo (MC) transport code. The McCARD code can utilize continuous energy cross section library and treat complex geometric information for particle transport simulation. Accordingly, the McCARD code can provide accurate solutions for burnup analyses without approximations, but it needs huge computing resources and time burden to perform whole-core follow calculations. Therefore, we will confirm the effectiveness of the single McCARD FA burnup analyses by comparing the DeCART2D/MASTER core follow results with the McCARD solution. From the results, the use of single FA burnup analyses for the establishment of the DBs will be justified. Various FAs, that have different 235U enrichments and loading pattern of fuel rods and burnable absorbers, were considered for the burnup analyses. In addition, the results of the sensitivity analyses for power density, initial enrichment, and cooling time will be presented.

본 연구에서는 유한요소해석 D/B를 기반으로 보간식을 산출하여 개활지 폭발현상에 의해 기둥에 작용하는 폭압이력을 예측하는 모델을 개발했다. D/B 구성을 위해 7종류 기둥 너비에 대해 총 70회의 유한요소해석을 수행했다. 제안하는 방법의 성능확인을 위해, 기존에 제시된 경험식 기반의 예측식과의 비교연구를 수행했다. 또한, D/B를 구성하는 point 외의 영역에서의 예측 정확도 확인을 위 해 유한요소해석 결과와의 비교/검증 연구를 추가로 수행했다. 제안하는 방법은 기존의 경험식 기반 예측식에 비해 유한요소해석 결 과와 유사한 결과를 산출함을 확인했다.

본고는 지지울라스의 삼위일체적 교회론을 선교적 관점으로 재해 석한 선교적 교회론 연구이다. 지지울라스는 성부의 인격 엑스타시스를 통해 삼위일체 하나님을 구성한 것처럼 세상을 구성하고, 종말론적 코뮤니온을 이루기 위해서 아들과 성령을 세상에 보내시며 코뮤니온을 이룬다고 주장한다. 그에게 선교는 코뮤니온이다. 그는 하나님의 존재 방식에 상응하는 교회로서 코뮤니온을 이루는 교회가 되어야 한다고 주장한다. 따라서 교회는 존재론적으로 코뮤니온 공동체를 이루는 선교적 차원을 가져야 하고, 지역교회와 교회 일치 운동은 코뮤니온 하나님의 선교에 참여하는 것이 된다. 그의 신학의 중심에 성찬식을 두어, 성만찬이 이루어지는 지역교회는 지역성과 보편성을 지니고 있어, 지역 문화에 배타적이지 않고, 코뮤니온을 이루되 교회성을 지키는 교회가 되어야 하며, 세상으로 보냄을 받은 교회는 교회중심으 로 모여 종말을 선취하는 교회가 되어야 한다고 보았다. 그의 코뮤니온 교회론은 개인주의와 배타주의를 극복하는 코뮤니온 선교적 교회가 된다.

2000년대 이후, 우리나라에서는 공립미술관이 대거 개관하면서 그 중요성을 새롭게 재인 식하는 시대를 맞이하였다. 이와 함께 공립작가미술관도 계속 증가해가며 그 입지를 더욱 강화해 가는 모습을 보여주고 있다. 요제프 슘페터는 새로운 것들의 끊임없는 결합과 적용을 통해 기존 의 것들을 혁신해나가는 ‘창조적 파괴’의 개념을 고안해냈다. 따라서 이 연구는 ‘이응노의집’에 초점을 맞춰 우리나라 공립작가미술관의 현황을 점검해보고, 창조적 파괴의 개념을 통해 이응노 의 예술세계를 기념하는 이응노의집의 미래경영 방안을 제언해 보고자 한다. 특히 이 연구는 근 대미술관이 부재한 한국의 미술관 현황을 고려하여 이응노의 예술세계를 핵으로 하는 근대미술 관으로 자리매김하는 이응노의집의 미래경영 전략과 방안을 구상해 보여주고자 한다.

Efficient capture and storage of radioactive iodine (consisting of two isotopes: 129I and 131I), produced or released from nuclear activities, are of paramount importance for sustainable development of nuclear energy due to their volatility and long half-life. Therefore, it is very important to develop new adsorbents for efficient utilization of radioactive iodine from nuclear waste. Various methods and materials are used for I2 capturing and removing, including MOFs due to their high porosity and fast adsorption kinetics, which are rightfully considered effective sorbents for removing I2. Metal–organic frameworks (MOFs) are porous crystalline materials which have diverse pore geometry and unique physicochemical properties, have attracted enormous attention for use in gas storage, separation and catalysis. The ability of MOFs to adsorb volatile products at room temperature can significantly improve the cost-effectiveness of the utilization process. This work describes the synthesis and characterization of three new metal-organic frameworks based on pyrazine (pyz), 44’bipyridine (bpy), 1,2 -bis(4 - pyridyl) – ethane (bpe) and copper (II) hexafluorozironate, as potential adsorbents for I2 capture. All of these three MOFs exhibit a two - dimensional (2D) crystal structure consisting from infinity non-crossing linear chains. The crystal structure of [Cu(pyz)2(ZrF6)2(H2O)2], [Cu(bpy)4(H2O)2ZrF6] and [Cu(bpe)4(H2O)2ZrF6] were characterized using powder X-ray diffraction (PXRD), single crystal X-ray diffraction (SC-XRD). Comparative characteristics of synthesized MOFs, including Fourier-transform infrared spectroscopy (FTIR) and thermogravimetric analysis (TGA) were also performed. The I2 sorption experiments were examined by UV-vis spectroscopy.

Gases such as hydrogen can generate from the disposal canister in high-level radioactive waste disposal systems owing to the corrosion of cooper container in anoxic conditions. The gas can be accumulated in the voids of bentonite buffer around the disposal canister if gas generation rates become larger than the gas diffusion rate of bentonite buffer with the low-permeability. Continuous gas accumulations result in the increase in gas pressure, causing sudden dilation flow of gases with the gas pressure exceeding the gas breakthrough pressure. Given that the gas dilation flow can cause radionuclide leakage out of the engineered barrier system, it is necessary to consider possible damages affected by the radionuclide leakage and to properly understand the complicated behaviors of gas flow in the bentonite buffer with low permeability. In this study, the coupled hydro-mechanical model combined with the damage model that considers two-phase fluid flow and changes in hydraulic properties affected by mechanical deformations is applied to numerical simulations of 1-D gas injection test on saturated bentonite samples (refer to DECOVALEX-2019 Task A Stage 1A). To simulate the mechanical behavior of microcracks which occur due to the dilation flow caused by increase in gas pressure, a concept of elastic damage constitutive law is considered in the coupled hydro-mechanical model. When the TOUGH-FLAC coupling-based model proposed in this study is applied, changes in hydraulic properties affected by mechanical deformations combined with the mechanical damage are appropriately considered, and changes in gas injection pressure, pore pressures at radial filters and outlet, and stress recorded during the gas injection test are accurately simulated.