목적 : 본 연구는 고등학생들이 학교에서의 장애 학생과 접촉 경험이 장애인에 대한 인식 및 관심에 미치는 영향을 알아보고 또한 시각장애 체험 프로그램의 유익성 평가에 미치는 영향에 대해 조사하고자 한다. 방법 : 비장애 고등학생(176명)을 대상으로 장애인에 대한 인식과 관심, 학교생활에서 접촉 경험 등에 관 한 설문조사를 진행하였으며, 시각장애 체험 장비를 활용하여 체험 프로그램을 진행 후 장애체험 관련 설문을 추가로 실시하였다. 자료 분석을 위하여 IBM SPSS Statistics 21.0을 통한 기술통계분석, 빈도분석, 다중회귀 분석 방법을 활용하였다. 결과 : ‘장애인에 대한 인식 및 관심’과 ‘시각장애 체험 프로그램 유익성 평가’ 와 관련된 세부 항목들에서 전반적으로 긍정적인 인식을 가지고 있는 것으로 확인되었다. 응답자의 학년이 높을수록, 장애 학생과 반에서 함께 생활 경험이 있는 응답자일수록 장애인에 대한 긍정적 인식이 높은 것으로 나타났다. ‘장애인에 대한 인 식’이 긍정적일수록 장애인에 대한 관심이 높은 것을 확인하였다. 응답자의 연령과 학년이 높을수록 시각장애 체험프로그램에 대한 평가가 긍정적으로 확인되었고, 장애 학생과 반에서 함께 생활한 경험이 없는 응답자일 수록 시각장애체험 프로그램에 대한 평가가 긍정적으로 나타났다. 결론 : 비장애 학생들의 장애인에 대한 인식과 관심이 전반적으로 긍정적이였으며 시각장애인과의 접촉 경 험이 적은 학생들에게 시각장애 체험프로그램을 적용 시 장애인에 대한 인식 및 관심을 제고시키는데 도움이 된다.

국립수산과학원은 과거 해양관측자료 복원사업을 통해 1961년 이전의 정선해양관측 및 연안정지관측 자료를 복원하여 디지털화 하였다. 먼저 한국근해 해양관측(정선해양관측) 자료 중 과거부터 현재까지 정점이 일치하는 21개 정점에 대한 지난 80년-92년간 표층 수온의 연변동을 분석한 결과 다소 차이는 있으나 상승 경향을 나타내었으며, 서해와 남해는 기존 연구와 동일하게 연안역보다 근해역에 위치한 정점에서 수온상승 경향이 높게 나타났다. 그러나 동해는 기존 연구와 달리 연안역보다 근해역에 위치한 정점에서 낮은 수온상승 경향을 나타내었다. 다음으로 복원된 연안정지관측 자료 중 각 동·서·남해를 대표할 수 있는 3개 정점에 대한 지난 89년-98년간 표층수온의 연변동을 살펴보면 동해(주문진, 1.63℃), 남해(거문도, 1.16℃). 서해(부도, 0.79℃)로 동해의 상승경향이 가장 뚜렷하였으며, 뚜렷한 주기 성은 파악하기 어려우나 대체로 3~6년을 주기로 상승과 하강을 반복함을 알 수 있었다. 특히 1980년대 이후 대부분 정점에서 양의 편차를 나타내었다. 마지막으로 해양-대기 상호작용을 이해하기 위해 연안정지관측정점의 표층수온변화에 따른 기온의 상관성을 분석한 결과 상관계수 값이 남해(거문도)는 0.76, 서해(부도)는 0.34, 동해(주문진)는 0.32로 남해가 가장 높게 나타났다.

The purpose of this study was to examine the effects of Maca water and/or ethanol extract on the nitric oxide (NO) production in human umbilical vein endothelial cells HUVAC and on erectile dysfunction in rats. Maca was extracted due to both solutions, which are water and ethanol. Each Maca extract was applied to HUVAC, and NO production was checked. Additionally, three different dosages (250, 500 and 1,000 mg/kg) of Maca ethanol extract was administered to Sprague-Dawley rats for 4 weeks. All rats were sacrificed and each sample was collected for analysis. The control rats received only the saline vehicle. The NO production of HUVAC was significantly increased by domestic and homemade Maca water extracted at 60℃ group. Both NO generation and testosterone release were not influenced due to the oral administration of Maca. In the EtOH group rats, the number of sperm was reduced compared to that of the control group. All Maca groups had a high number of sperm and each sperm count had increased as a result of the Maca extract dose. The results of this research suggest that Maca has a positive effect on male erectile dysfunction, which need to be examined further in future studies.

Radioactive source terms are important factor in design, licensing and operation of SMR (Small Modular Reactor). In this study, regulatory requirements and evaluation methodology for normal operation on NuScale SMR, which received standard design certification approval on September 11, 2020 from US NRC, are reviewed. The radioactive waste management system of nuclear power reactor should be designed to limit radionuclide concentration in effluents and keep radioactive effluents at restricted area boundary ALARA according to 10 CFR 20 and 10 CFR 50 Appendix I. Also, in general, the coolant source term to calculate the off-site radiological consequences for normal operation of SMR should be determined by using models and parameters that are consistent with regulatory guide 1.112, NUREG- 0017 and the guidance provided in ANSI/ANS-18.1-1999, and the result should be corrected by reflecting the design characteristics of SMR. The coolant source term of NuScale, unlike the case of large NPPs, cannot rely solely on empirical source term data, because the NuScale source term is based on first principle physics, operational experience from recent industry, and lessons learned from large PWR operation. Fission products in reactor coolant are conservatively calculated using first principle physics in SCALE Code assuming 60 GWD/MTU. The release of fission products from fuel to primary coolant based on industry operational experience is determined as fuel failure fraction of 0.0066% for normal operation source term and 0.066% for design basis source term while coolant source term of large NPP is calculated by using ANSI/ANS-18.1 for normal operation and fuel failure fraction of 1% for design basis source term. Water activation products in reactor coolant are calculated from first principles physics and corrosion activation products are calculated by utilizing current large PWR operating data (ANSI/ANS 18.1- 1999) and adjusted to NuScale plant parameters. Also, because ANSI/ANS 18.1-1999 is not based on first principle physics models for CRUD generation, buildup, transport, plate-out, or solubility, NuScale has incorporated lessons learned by using ERPI’s primary water chemistry and steam generator guidelines to ensure source term is conservative and design of materials used cobalt reduction philosophy to help ensure the coolant source term are conservative. Based on the coolant source term calculated according to the above-described method, the annual releases of radioactive materials in gaseous and liquid effluents from NuScale reactor are evaluated. Currently, Small Modular Reactors such as ARA, SMART 100 are under review for licensing in Korea. This study will be helpful to understand how the reactor coolant system source terms are defined and evaluated for SMR.

In Korea, the NUREG-0017 methodology based on realistic model for reactor coolant concentrations are used to estimate the annual radioactive effluent releases for normal operation of nuclear power plant. The realistic model to estimate the radionuclide concentrations in reactor coolant is formulated as a standard, ANSI/ANS-18.1. This standard has provided a set of the reference radionuclide concentrations and adjustment factors for estimating the radioactivity in the principal fluid systems of target plant. Since ANSI/ANS-18.1 was first published in 1976, it was revised in 1984, 1999, 2016, and most recently in 2020. Therefore, this study analyzed revision history of assessment methodology of radioactive source term of light water reactors, which is ANSI/ANS-18.1. Assessment methodology of radioactive source term given ANSI/ANS-18.1 is by using radionuclide concentrations for reactor coolant and steam generator fluid of the reference plant and adjustment factors, which is modifying radioactive source term according to differences in design parameters between reference plant and target plant. There are three type of reference plant: PWR with u-tube steam generator, PWR with once-through steam generator, and BWR. This study analyzed for PWR with u-tube steam generator. Although the standard was revised, evaluation methodology and formula of adjustment factor have been retained, but some of items have been revised. First revision item is reduction of the number of radionuclides and decrease of radioactive concentration in reactor coolant. In the 1976 version of the standard, there were 71 target radionuclides, but the target nuclides have reduced to 57 in 1984 and 56 after 1999. In the case of radioactive concentration in reactor coolant, as the version of standard was updated, the radioactive concentration of 18 nuclides in 1984, 14 nuclides in 1999, and 25 radionuclides in 2016 was decreased. Most of the radionuclides with decrease radioactivity concentration were fission product, it is resulted from improvement of nuclear fuel performance. Second revision item is change of adjustment factors. After the revision in 2016, the adjustment factors for zinc addition plants using natural or depleted zinc are changed. This study analyzed revision history of evaluation methodology of radioactive source term of light water reactors. Furthermore, result of this study will be contributed to the improvement of understanding of assessment methodology and revision history for the radioactive source term.

In order to breed the useful mutants in black raspberry, cultivated in Gochang-gun, leaf-petiol explants from shoot-proliferating culture was regenerated after irradiated with 30, 50 and 70 Gy gamma-ray. The LD50 dose of leaf-petiol explants was identified as 30Gy after two months. Morphological characteristics of the variants were observed such as stem variation, existence and nonexistence of spine, spine color, anthocyanin content, width of leaf, thick of leaf compared with donor cultivar. Of the 701 mutants, 14 lines with the useful mutant characters were selected and random amplified polymorphic DNA(RAPD) was carried out to confirm mutation state at the molecular level with 20 primers. There are many bands be revealed only in mutants and disappear in mutants reversely. RAPD analysis revealed a high level of genetic diversity among Control and mutants. Compared to Control, No. 14 mutant showed the highest genetic diversity. Also, the co-dominant SSR markers have allowed the evaluation of heterozygosity. Valuable mutants obtained will be useful for developing new cultivars and studying gene function in molecular level.