• Nuclear Engineering and Technology
• /
• 제15권4호
• /
• pp.248-255
• /
• 1983

하나의 PWR 핵연료 집합체를 수송할 수 있는 사용후 핵연료 수송용기에 대한 열해석을 수행하였다. 정상 및 화재사고 조건하에서 수송용기에 대한 온도분포는 10CFR Part 71에서 제시한 조건에 맞도록 계산하였다. 붕괴열은 연소도가 45,000 MWD/MTU이고 사용후 핵연료 저장실에서 300일 냉각기간을 가질 KNU 5&6 핵연료 집합체를 고려하였다. 계산결과 화재사고시 dry cavity조건하에서 핵연료 피복관의 최대온도가 455$^{\circ}C$로 계산되었으며, 이 간은 10CFR Part 50.46에 규정된 최대 피복관 제한치 보다 훨씬 낮게 나타났다. 이것은 수송용기의 운반중에 화재사고 조건하에서도 핵연료 피복관의 파손이 일어나지 않는 것으로 설명된다. 그리고 중요 차폐체인 납의 용융도 일어나지 않았다.

• Physical Therapy Rehabilitation Science
• /
• 제9권2호
• /
• pp.82-89
• /
• 2020

Objective: The purpose of this study was to assess the effect of hospital-based pulmonary rehabilitation (PR) on exercise capacity and quality of life as well as barriers to participation in persons with chronic obstructive pulmonary disease (COPD) in South Korea. Design: One-group pretest-posttest design. Methods: A total of 14 patients were enrolled in this study in an 8-week PR program with two 60-minute sessions per week. The program included: flexibility exercises, breathing techniques, strengthening exercises, and aerobic exercises. The outcomes were defined as changes in the variables before and after the PR program. A change in the 6-minute walk distance (6MWD) was defined as the primary outcome, and changes in pulmonary function test, respiratory and grip strength, and the St. George's Respiratory Questionnaire (SGRQ) about quality-of-life results were secondary outcomes. A dropout was defined as missing >3 of the 16 sessions. Results: Patients who completed the program showed a significant improvement of 43.57±39.43 m in the 6MWD (p<0.05), but no significant differences were noted for the other function tests. The SGRQ showed a significant improvement in the activity and total score (p<0.05). The total dropout rate was 53.3%. Newly developed symptoms, exacerbation of COPD, transport problems, and lack of motivation were major barriers to PR. Conclusions: Our study showed that an 8-week hospital-based PR program improved exercise capacity and quality of life but had a high dropout rate in individuals with COPD. Since comprehensive PR has only recently been established in South Korea, patient motivation and education are critical.

• 한국안전학회지
• /
• 제27권6호
• /
• pp.78-83
• /
• 2012

In this study, some experimental results of the peroxide-degradation process of polypropylene(PP) in a co-rotating twin-screw extruder to produce controlled rheology polypropylene(CRPP) are presented. The peroxide was dicumyl peroxide(DCP) and the concentration of DCP was in the range 0-0.3 wt%. It was found that the rheological properties of PP change significantly during reactive extrusion. Melt flow index(MFI) increased with DCP concentration. Intrinsic viscosity decreases with increasing DCP concentration. From dynamic rheological data, number average molecular weight(Mn), weight average molecular weight(Mn) and molecular weight distribution(MWD) were calculated. Results indicated that Mw decreases and MWD becomes narrower with increasing peroxide concentration. Especially, particle size distribution of CRPP decreases with increasing DCP concentration by chemical powdering process, and anti-slip floor paint, CRPP(DCP 0.2 wt%) powder by 10phr was friction coefficient 2.15 ${\mu}$, abrasion resistance 511.18%.

• Nuclear Engineering and Technology
• /
• 제13권1호
• /
• pp.1-11
• /
• 1981

가압경수로심의 3차원적 simulation 코드인 KINS를 개발하여 고리1호기 제 1주기에 대한 benchmark 계산을 수행하였다. KINS는 FLARE에서 사용하고 있는 모델을 기초로 하여 가압경수로심 해석에 보다 유용하게 쓸 수 있도록 발전시킨 것이다. 제 1주기초에서는 hot zero power 상태에서의 임계붕소농도, 핵연료집합체별 출력분포, 노심평균축방향 출력분포 등을 계산하여 실측 자료와 비교하였다. 아울러 연소도 1000MWD/MTU 단위로 연소계산을수행하여 여기서 산출된 임계 붕소농도와 핵 연료집합체별 출력 분포를 실측자료와 비교하였다. 계산결과는 실측자료와 매우 훌륭하게 일치하고 있으므로 KINS가 가압경수로의 노심관리에 아주 경제적이며 유효한 도구가 될것임을 보여주는 것이라고 생각된다.

• 대한한의학회지
• /
• 제43권1호
• /
• pp.171-179
• /
• 2022

본 증례에서는 COVID-19 후유증기에 호흡곤란을 주소로 내원한 환자에 대하여 한방 호흡재활치료를 시행한 결과 호흡곤란, 기침 등의 증상 및 삶의 질에 임상적으로 의미 있는 호전이 있었고, 향후 COVID-19 후유증 환자에 한방 치료를 활용할 수 있음을 제시하였기에 증례를 보고하는 바이다.

• Nuclear Engineering and Technology
• /
• 제25권2호
• /
• pp.248-254
• /
• 1993

본 연구에서는 법규에서 규정하고 있는 주변온도 38$^{\circ}C$의 정상수송조건하에서 수송용기의 건식수송조건에 대한 열해석을 평가하였다. 수송용기는 1회에 PWR 핵연료집합체 4개를 운반할 수 있는 용량을 가지며, 설계기준 핵연료는 연소도 38,000 MWD/MTU, 냉각기간 3년을 기준으로 하였다. 건식수송조건에 대한 열해석을 평가하기 위하여 COBRA-SFS 전산코드를 이용하였다. 수송용기 내부 cavity에 공기, 질소 및 헬륨가스를 채우는 세가지 조건에 대한 해석을 수행하였으며, 최대 핵연료봉의 온도는 수송용기 내부 cavity가 공기인 경우에는 277$^{\circ}C$, 헬륨인 경우에는 226$^{\circ}C$로 계산되었다. 이 값은 건식수송조건에서 수송용기 내부에 장전된 PWR 핵연료집합체가 열적으로 건전성을 유지하기 위한 규정온도보다 낮은 것으로 나타났다.

• Nuclear Engineering and Technology
• /
• 제41권2호
• /
• pp.179-186
• /
• 2009

This paper presents a thermal creep test under internal pressure and post-test characterization performed on high burnup (68 MWd/kgU) ZIRLO. This research has been done by the CSN, ENRESA, and ENUSA in order to investigate the behavior of advanced cladding materials in contemporary PWRs at higher burnup under dry cask storage conditions. Also, to investigate the hydride reorientation, the cool-down of the samples after the test has been done in a coordinated manner with the internal pressure. The creep results obtained are consistent with the expected behavior from reference CWSR material, Zr-4. During the test, the material retained significant ductility: one specimen leaked during the test at an engineering strain of the tube section of 17%; remarkably, the crack closed due to de-pressurization. Although significant hydride reorientation occurred during the cool-down under pressure, no specimen failed during the cool-down.

• 한국환경과학회지
• /
• 제7권1호
• /
• pp.104-111
• /
• 1998

The Dongbok lake water before and after alum coagulation and activated carbon adsorption were analyzed in terms of organic contents, molecular weight distributuin (MWD), and UV-absorbance. Dissolved organic compounds in the Dongbok lake were fractionated into three molecular size classes by gel permeation chromatography. The fractionation was reasonably successful in isolating compounds with The bulk of the dissolved carbon was present in compounds of molecular weight in the range of 3,000~10,000. Alum coagulation preferentially treated molecules of high molecular weight, which has molecules larger than 10,000. The dissolved organic carbon (DOC) removal after activated carbon adsorption was high in the Fraction B , IR . The $A_{260}$/DOC ratio after alum and activated carbon treatment the Fraction II, III. This results suggest that the organics remaining after each treatment has a trihalomethane formation potential

• 한국분말재료학회지
• /
• 제6권3호
• /
• pp.209-214
• /
• 1999

The oxidation behavior of the simulated spent fuel of burn up 33 MWD/kgU was investigated to predict that of the spent fuel in the temperature ranges of 400 to $700^{\circ}C$ and was compared with those of $UO_2$. The forms of uranium oxides after the oxidation were conformed by XRD analyses. The oxidation rate at each the temperature and the activation energy were obtained. After complete oxidation, the simulated spent fuel was converted to $U_3O_8$ and pulverized to powder due to the density difference between the simulated spent fuel and uranium oxides. The activation energies were 85.35 and 30.77kJ/mol in the temperature ranges of 400$\leq$T($^{\circ}C$)$\leq$500 and 500$\leq$T($^{\circ}C$)$\leq$700, respectively.

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2009년도 학술논문요약집
• /
• pp.311-312
• /
• 2009

가압 경수로에서 53,000 MWd/tU으로 연소된 사용후 핵연료의 PCI 영역에 대해 방사선 차폐형 성분 분석기기( Shielded EPMA)를 사용하여 반경방향에 대한 성분분포를 분석하였다. PCI 영역에서 산화층의 두께는 13um 이었으며, 핵분열생성물의 침투 두께는 시료에서 약 10 um 이내로 나타났다. 이 두께에 침투된 핵종의 총 농도는 1~2 wt%로 관찰되었다. 주요핵종은 Cs 0.5~0.7 wt%, Mo 0.2~0.3 wt%, Pd, Ru, Nd, Ce등이 0.1~0.2 wt% 로 관찰되었다.