• Proceedings of the Korean Nuclear Society Conference
• /
• 2005.05a
• /
• pp.601-602
• /
• 2005

• Proceedings of the Korean Nuclear Society Conference
• /
• 2005.10a
• /
• pp.665-666
• /
• 2005

• Proceedings of the Korean Nuclear Society Conference
• /
• 2005.10a
• /
• pp.685-686
• /
• 2005

• Proceedings of the Korean Nuclear Society Conference
• /
• 2005.10a
• /
• pp.410-411
• /
• 2005

• Nuclear Engineering and Technology
• /
• v.55 no.5
• /
• pp.1559-1566
• /
• 2023

This study developed a quasi-monoenergetic neutron source (QMN) for the semiconductor device's soft error rate test (SER). Quasi-monoenergetic neutrons are generated by ⁹Be(p, n)⁹B nuclear reaction with a 1 mm beryllium target and 30 MeV protons from a cyclotron. An 8 mm water in the back of the beryllium target is used for avoiding proton penetration. The neutron spectra simulated by MCNP showed that the peak energy was around 26.5 MeV. The heat flow and mechanical properties are numerically analyzed, and the safe operating conditions are therefore determined.

• Journal of the Korean Ceramic Society
• /
• v.42 no.8 s.279
• /
• pp.575-581
• /
• 2005

SiC-based ceramics are considered as candidate materials for the advanced nuclear energy systems such as the generation IV reactors and the fusion reactors due to their excellent high-temperature strength and irradiation resistance. The advanced nuclear energy systems and their main components adopting ceramic composites were briefly reviewed. A novel fabrication method of $SiC_f/SiC$ composites by introducing SiC whiskers was also described. In addition, the charged-particle irradiation ($Si^{2+}$ and $H^{+}$ ion) into CVD SiC was carried out to simulate the severe environments of the advanced nuclear reactors. SiC whiskers grown in the fiber preform increased the matrix infiltration rate by more than $60\%$ compared to the conventional CVI process. The highly crystalline and pure SiC showed little degradation in hardness and elastic modulus up to a damage level of 10 dpa at $1000^{\circ}C$.

• Proceedings of the KIEE Conference
• /
• 2008.10b
• /
• pp.540-541
• /
• 2008

원자력 발전소 격납구조(containment) 내에 설치되는 센서, 구동기(actuator) 및 설비는 원전의 안전운전과 함께 방사능 누출사고와 같은 중대사고(severe accident)를 예방하기 위한 것이다. 격납구조 내부는 Category I 등급으로 분류되며, 격납구조 내부에 설치되는 센서, 구동기, 기기 및 통신망은 IEEE Std. 323-1974에서 정의하는 극한환경(harsh environment) 요건에서 생존할 수 있는 내환경성이 요구된다. 이러한 엄격한 내환경성 요건으로 인해 일반 산업의 IT 기반 센서통신망이 원전 격납건물 내부에는 적용되지 않고 있다. 최근에 이르러 독일을 중심으로 신규로 건설 중이거나 계획 중인 원전에서는 일반 산업의 IT 기반 센서 통신망 적용이 검토되고 있다. 본 논문에서는 IT 기반의 첨단 센서 통신망 기술을 격납구조내부와 같은 극한 환경에 적용하기 위한 방안을 제시하고자 한다. 정상운전중의 원전 격납 건물 내부의 환경(온도, 감마선, 습도) 특성과 중대 사고를 가정한 DBA (설계 기준사고) 요건에서의 환경 특성을 조사하였다. 또한 설계기준사고에서 정의한 감마선 조사 환경에서 통신 시스템의 생존성을 실험하였다. 이를 토대로 격납구조내부의 원전 극한 환경 통신망의 개선방안을 제시하고자 한다.

• Bulletin of the Korean Chemical Society
• /
• v.32 no.12
• /
• pp.4327-4331
• /
• 2011

A new method in thermal ionization mass spectrometry (TIMS) was developed to correct peak tailing backgrounds in the isotope ratio measurements of uranium in ultra trace levels for higher accuracy. Two different uranium standard reference materials (U005 and U030) were used to construct databases of signal intensities at mass 234 u and mass 236 u, which correspond to the two uranium minor isotopes, and signal intensity of $^{238}U$. Correlations between peak tailing backgrounds and $^{238}U$ were obtained by least-squares regression on calculated backgrounds at mass 234 u and mass 236 u with respect to the signal intensity of $^{238}U$ followed by separation of the peak tails of the two major isotopes of uranium ($^{235}U$ and $^{238}U$), which enables us to obtain a master equation for peak tailing background correction on all kinds of samples. Verification of the correction method was carried out using U010 and IRMM-040a.

• Nuclear Engineering and Technology
• /
• v.49 no.4
• /
• pp.752-759
• /
• 2017

The fatigue crack growth behavior of Type 347 (S347) and Type 347N (S347N) stainless steel was evaluated under the operating conditions of a pressurized water reactor (PWR). These two materials showed different fatigue crack growth rates (FCGRs) according to the changes in dissolved oxygen content and frequency. Under the simulated PWR conditions for normal operation, the FCGR of S347N was lower than that of S347 and insensitive to the changes in PWR water conditions. The higher yield strength and better corrosion resistance of the nitrogen-alloyed Type 347 stainless steel might be a main cause of slower FCGR and more stable properties against changes in environmental conditions.

• Proceedings of the KIEE Conference
• /
• 2009.07a
• /
• pp.1823_1824
• /
• 2009

원자력 발전소 운전과정에서 발생하는 각종 폐액은 저장/여과 과정을 거치게 된다. 이러한 폐액의 저장/여과 과정에서 탱크 내에 침적된 방사성 슬러지들은 농축 고화 처리가 요구 되며 방사선량에 따라 작업자의 접근이 제한적이다. 본 논문에서는 탱크나 섬프(Sump)내의 방사성 슬러지를 제거하기 위하여 개발 중인 로봇의 기능과 이를 이용한 슬러지 제거 기초실험 결과를 제시한다.