• Nuclear Engineering and Technology
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• 제47권3호
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• pp.380-387
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• 2015

A lead slowing-down spectrometer (LSDS) system is a promising nondestructive assay technique that enables a quantitative measurement of the isotopic contents of major fissile isotopes in spent nuclear fuel and its pyroprocessing counterparts, such as $^{235}U$, $^{239}Pu$, $^{241}Pu$, and, potentially, minor actinides. The LSDS system currently under development at the Korea Atomic Energy Research Institute (Daejeon, Korea) is planned to utilize a high-flux ($>10^{12}n/cm^2{\cdot}s$) neutron source comprised of a high-energy (30 MeV)/high-current (~2 A) electron beam and a heavy metal target, which results in a very intense and complex radiation field for the facility, thus demanding structural shielding to guarantee the safety. Optimization of the structural shielding design was conducted using MCNPX for neutron dose rate evaluation of several representative hypothetical designs. In order to satisfy the construction cost and neutron attenuation capability of the facility, while simultaneously achieving the aimed dose rate limit (< $0.06{\mu}Sv/h$), a few shielding materials [high-density polyethylene (HDPE)eBorax, $B_4C$, and $Li_2CO_3$] were considered for the main neutron absorber layer, which is encapsulated within the double-sided concrete wall. The MCNP simulation indicated that HDPE-Borax is the most efficient among the aforementioned candidate materials, and the combined thickness of the shielding layers should exceed 100 cm to satisfy the dose limit on the outside surface of the shielding wall of the facility when limiting the thickness of the HDPE-Borax intermediate layer to below 5 cm. However, the shielding wall must include the instrumentation and installation holes for the LSDS system. The radiation leakage through the holes was substantially mitigated by adopting a zigzag-shape with concrete covers on both sides. The suggested optimized design of the shielding structure satisfies the dose rate limit and can be used for the construction of a facility in the near future.

• 한국결정성장학회지
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• 제16권6호
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• pp.235-239
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• 2006

Micro-pulling down$({\mu}-PD)$법을 이용하여 직경 $0.8{\sim}1.0mm$, 길이 $30{\sim}35mm$의 ZnO가 첨가된 near-stoichiometric $LiNbO_3$, 단결정을 성장하였다. 성장된 결정의 결정구조를 powder x-tay diffraction(XRD) patterns으로 확인하였고, electron probe micro analysis(EPMA)를 이용하여 결정내 Zn 이온들이 균일하게 분포되었음을 확인하였다. 또한 2 mol% 이상의 ZnO 첨가시 $OH^-$ 흡수밴드의 특성이 크게 변화함을 관찰함으로써 ZnO 첨가량에 일치한 역치(threshold)가 존재함을 확인하였다.

• Child Health Nursing Research
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• 제22권3호
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• pp.227-235
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• 2016

Purpose: The purpose of this study was to identify the relationship between self-esteem and sexual attitude in healthcare college students, and also to provide a basis for sexual health education programs to help establish healthy sexual attitudes. Methods: A survey was conducted with 218 unmarried students attending the healthcare colleges in B and U cities. Data were collected from October 15 to November 10, 2015 and analyzed using Stepwise multiple regression with SPSS PASW 18.0. Results: Mean score for self-esteem was $3.23{\pm}0.46$ out of 5 and sexual attitude $2.64{\pm}0.54$ out of 5. Self-esteem and sexual attitude had a negative correlation (r=-.169, p=.012). Among sub-variables of sexual attitude, negative correlations were found between self-esteem and premarital chastity (r=-.207, p=.002), and between self-esteem and homosexual attitudes (r=-.167, p=.013). There were statistically significant differences in sexual attitude according to perceived intimacy with mother (${\beta}$=-.228, p<.001), year in college (${\beta}$=.135, p=.047), major (${\beta}$=.148, p=.023), religion (${\beta}$=-2.429, p=.016), and homosexual tendencies (${\beta}$=.139, p=.037). These factors explained 14.6% of the variance in sexual attitude. Conclusion: Findings demonstrate the importance of self-esteem for sexual attitudes. This finding should be used in the development of healthcare college students, promotion programs to enhance healthy sexual attitudes.

• Restorative Dentistry and Endodontics
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• 제40권3호
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• pp.229-235
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• 2015

Objectives: To determine and compare the fracture resistance of endodontically treated maxillary central incisors restored with different posts and cores. Materials and Methods: Forty-eight upper central incisors were randomly divided into four groups: cast post and core (group 1), fiber-reinforced composite (FRC) post and composite core (group 2), composite post and core (group 3), and controls (group 4). Mesio-distal and bucco-lingual dimensions at 7 and 14 mm from the apex were compared to ensure standardization among the groups. Twelve teeth were prepared for crown restoration (group 4). Teeth in other groups were endodontically treated, decoronated at 14 mm from the apex, and prepared for posts and cores. Resin-based materials were used for cementation in groups 1 and 2. In group 3, composite was used directly to fill the post space and for core build-up. All samples were restored by standard metal crowns using glass ionomer cement, mounted at $135^{\circ}$ vertical angle, subjected to thermo-mechanical aging, and then fractured using a universal testing machine. Kruskal-Wallis and Mann-Whitney U tests were used to analyze the data. Results: Fracture resistance of the groups was as follows: Control (group 4) > cast post and core (group 1) > fiber post and composite core (group 2) > composite post and core (group 3). All samples in groups 2 and 3 fractured in restorable patterns, whereas most (58%) in group 1 were non-restorable. Conclusions: Within the limitations of this study, FRC posts showed acceptable fracture resistance with favorable fracture patterns for reconstruction of upper central incisors.

• 한국콘텐츠학회논문지
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• 제13권9호
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• pp.227-235
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• 2013

본 연구는 자아존중감 향상 프로그램이 한부모 가정 초등학생의 자아존중감과 우울에 미치는 효과를 검증하기 위해 실시되었다. 연구에 참여한 대상자들은 본 프로그램에 동의한 두 개의 초등학교 한부모 가정 아동 중 지원자를 받아 A학교를 실험군(12명)으로, B학교를 대조군(13명)으로 임의 배정하고 프로그램 시작 전에 자아존중감과 우울 척도를 이용하여 사전 검사를 실시하였다. 실험군에게는 한부모 가정 초등학생을 위한 자아존감향상 프로그램을 제공하였다. 실험처치는 실험군 12명을 6명씩 2집단으로 나누어 주 1회 40분씩 총 10회기를 진행하였다. 프로그램 종료 후 실험군, 대조군에게 자존감과 우울 척도를 이용하여 사후 검사를 실시하였다. 사후 검사에서 실험군 1명의 자료가 결측되어 최종 실험군 11명, 대조군 13명의 자료가 수집되었다. 연구결과 대조군 보다 실험군이 유의한 수준에서 자아존중감이 증가(z=-2.499, p<.012, ES(d)=0.7)하고, 우울이 감소(z=-2.145, p<.032, ES(d)=-0.4) 되었다. 이러한 결과는 본 연구의 프로그램이 한부모 가정 초등학생들의 심리사회적 적응을 위해 유용하게 사용될 수 있음을 시사한다.

• 한국농림기상학회지
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• 제6권4호
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• pp.235-241
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• 2004

1월의 최저기온을 대상으로 1951년부터 2000년까지 14개 지점의 관측자료를 분석한 결과 11개 지점에서 전반기(1951-1980)에 비해 후반기(1971-2000)의 연차 변이가 오히려 감소한 것으로 나타났다 표준편차로 표현할 경우 제주, 전주, 울릉도를 제외한 나머지 11개 지점에서 많게는 0.35(서울)에서 적게는 0.03(강릉)까지 고르게 연차변이가 감소하였다. 이는 최근의 난동화 경향과 함께 겨울철 최저기온의 연차변이가 더 심해지고 있다는 당초의 예상과 다른 결과이다 연차변이의 공간분포양상은 최저기온의 절대값과 정의 상관을, 관측점의 해발고도와는 부의 상관을 보였다. 이 관계를 이용하여 남한전역의 1월 최저기온 30년 표준 편차 분포도를 작성하였으며, 이를 토대로 재현기간별로 기대되는 전국의 극최저기온 분포도를 제작하여 지역별 동해위험 평가에 이용토록 하였다.

• Restorative Dentistry and Endodontics
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• 제25권2호
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• pp.235-242
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• 2000

The purpose of this in vitro study was to evaluate the sealing ability of three sealers(Sealapex, Pulp canal sealer, AH26) used with continuous wave method using an anaerobic bacterial leakage model. 53 extracted human teeth with straight and single canals were prepared with crown-down pressureless technique using .04, .06 taper Profile(Maillefer, Swiss). Master apical file was maintained as #35 K-file. All canals of the experimental teeth were obturated with continuous wave method using System B(Analytic technology, U.S.A.) The teeth were randomly divided into three experimental groups of 15 and two control groups of 4. Experimental group 1 was obturated with Sealapex and group 2 with Pulp canal sealer, and group 3 with AH26. A dual chamber anaerobic bacterial leakage model was assembled. Brain heart infusion with yeast extract, hemin, menadion, and the chromogenic indicator bromocresol purple was used as the culture broth for Fusobacterium nucleatum(VPI 10197), The specimens were incubated in anaerobic chamber at $37^{\circ}C$ and were observed every 2 to 3 clays, The coronal leakage was evaluated through the color change of culture broth in lower chamber for 60 days. The results were as follows: 1. The incidence of bacterial leakage in group 1 (Sealapex group was 80%, 53% in group 2 (Pulp canal sealer), 27% in group 3 (AH26). 2. There were statistically significant differences in leakage scores between group 1 and group 2, and between group 1 and group 3, respectively. (P<0.05) 3. There was no significantly difference in leakage score between group 2 and group 3. (P>0 05)

• Nuclear Engineering and Technology
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• 제47권7호
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• pp.791-803
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• 2015

The effective cross sections (XSs) in the direct whole core calculation code nTRACER are evaluated by the equivalence theory-based resonance-integral-table method using the WIMS-based library as an alternative to the subgroup method. The background XSs, as well as the Dancoff correction factors, were evaluated by the enhanced neutron-current method. A method, with pointwise microscopic XSs on a union-lethargy grid, was used for the generation of resonance-interference factors (RIFs) for mixed resonant absorbers. This method was modified by the intermediate-resonance approximation by replacing the potential XSs for the non-absorbing moderator nuclides with the background XSs and neglecting the resonance-elastic scattering. The resonance-escape probability was implemented to incorporate the energy self-shielding effect in the spectrum. The XSs were improved using the proposed method as compared to the narrow resonance infinite massbased method. The RIFs were improved by 1% in $^{235}U$, 7% in $^{239}Pu$, and >2% in $^{240}Pu$. To account for thermal feedback, a new feature was incorporated with the interpolation of pre-generated RIFs at the multigroup level and the results compared with the conventional resonance-interference model. This method provided adequate results in terms of XSs and k-eff. The results were verified first by the comparison of RIFs with the exact RIFs, and then comparing the XSs with the McCARD calculations for the homogeneous configurations, with burned fuel containing a mixture of resonant nuclides at different burnups and temperatures. The RIFs and XSs for the mixture showed good agreement, which verified the accuracy of the RIF evaluation using the proposed method. The method was then verified by comparing the XSs for the virtual environment for reactor applicationbenchmark pin-cell problem, as well as the heterogeneous pin cell containing burned fuel with McCARD. The method works well for homogeneous, as well as heterogeneous configurations.

• Nuclear Engineering and Technology
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• 제49권3호
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• pp.549-555
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• 2017

A lead slowing-down spectrometer (LSDS) system is under development to analyze isotopic fissile content that is applicable to spent fuel and recycled material. The source neutron mechanism for efficient and effective generation was also determined. The source neutron interacts with a lead medium and produces continuous neutron energy, and this energy generates dominant fission at each fissile, below the unresolved resonance region. From the relationship between the induced fissile fission and the fast fission neutron detection, a mathematical assay model for an isotopic fissile material was set up. The assay model can be expanded for all fissile materials. The correction factor for self-shielding was defined in the fuel assay area. The corrected fission signature provides well-defined fission properties with an increase in the fissile content. The assay procedure was also established. The assay energy range is very important to take into account the prominent fission structure of each fissile material. Fission detection occurred according to the change of the Pu239 weight percent (wt%), but the content of U235 and Pu241 was fixed at 1 wt%. The assay result was obtained with 2~3% uncertainty for Pu239, depending on the amount of Pu239 in the fuel. The results show that LSDS is a very powerful technique to assay the isotopic fissile content in spent fuel and recycled materials for the reuse of fissile materials. Additionally, a LSDS is applicable during the optimum design of spent fuel storage facilities and their management. The isotopic fissile content assay will increase the transparency and credibility of spent fuel storage.

• Nuclear Engineering and Technology
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• 제50권8호
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• pp.1324-1329
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• 2018

This study presents a practical application of complementary safety indicators, which can be applied in a safety assessment of a radioactive waste repository by excluding a biosphere simulation and comparing the artificial radiation originating from the repository with the background natural radiation. Complementary safety indicators (radiotoxicity flux from geosphere and radiotoxicity concentration in seawater) were applied in the safety assessment of a rock-cavern type low and intermediate level radioactive waste (LILW) repository in the Republic of Korea. The natural radionuclide ($^{40}K$, $^{226,228}Ra$, $^{232}Th$, and $^{234,235,238}U$) concentrations in the groundwater and seawater at the Gyeongju LILW repository site were measured. Based on the analyzed concentrations of natural radionuclides, the levels of natural radiation were determined to be $8.6{\times}10^{-5}$ - $8.0{\times}10^{-4}Sv/m^2/yr$ and $6.95{\times}10^{-5}Sv/m^3$ for radiotoxicity flux from the geosphere and radiotoxicity concentration in seawater, respectively. From simulation results obtained using a Goldsim-based safety assessment model, it was determined that the radiotoxicity of radionuclides released from the repository is lower than that of the natural radionuclides inherently present in the natural waters. The applicability of the complementary safety indicators to the safety case was discussed with regard to reduction of the uncertainty associated with biosphere simulations, and communication with the public.