• Nuclear Engineering and Technology
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• v.27 no.5
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• pp.767-774
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• 1995

Behavior of radionuclides such $^{60}$ Co, $^{54}$ Mn and $^{137}$ Cs in the incineration Process was Studied by trial burns of simulated wastes with radio-isotope tracers. Behavior of nonvolatiles, $^{60}$ Co and $^{54}$ Mn, was similar to that of particulate matters in the process. Decontamination factors(DFs) for $^{60}$ Co and $^{54}$ Mn were 4.7$\times$10$^{5}$ and 6.2$\times$10$^{5}$ , respectively. Behavior of semivolatile radio-isotope, $^{137}$ Cs, was temperature dependent. DFs for $^{l37}$Cs at In different incineration temperature of 85$0^{\circ}C$ and $700^{\circ}C$ were 2.8$\times$10$^3$ and 2.6$\times$10$^4$, respectively. Trial bums of dry active waste(DAW) transported from nuclear power station(NPS) Kori 3,4 were also performed. DF for gross $\beta$/${\gamma}$ radioactivity in DAW was 1.1$\times$10$^{5}$ . This was a little higher than the estimated value, which was calculated from the tracer test results and nuclides distribution in the DAW. Average emission concentration was 0.019 Bq/N $m^3$, which could meet the maximal permissible concentration(MPC) in stack emission.n.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.17 no.2
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• pp.167-181
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• 2019

Currently, the development of evaluation technology for vibration and shock load characteristics and spent nuclear fuel structural integrity under normal conditions of transport is being conducted in the Republic of Korea. This is the first such research conducted in the Republic of Korea and, thus, previous international studies need to be investigated and will be referred to in the ongoing project. Before 2000, several studies related to measurement of vibration and shock loads on spent nuclear fuel were conducted in the US. US national research institutes conducted uniaxial fuel assembly shaker tests, concrete block tests, and multi-axis fuel assembly tests between 2009 and 2016. In 2017, multi-modal transportation tests including road, sea, and rail transport were also performed by research institutes from the US, Spain and the Republic of Korea. Therefore, test preparation procedures, acceleration and strain measurement results, and finite-element and multi-body dynamics analysis were investigated. Based on the measured strain data, the preliminary conclusion was obtained that the measured strain was too small to cause damage to spent nuclear fuel rods. However, this conclusion is a preliminary conclusion that only reviews part of the results; a detailed review is being conducted in the US. The investigation of international studies on spent nuclear fuel structural integrity tests considering vibration and shock loads under normal conditions of transport in the US will be useful data for the project being conducted in the Republic of Korea.

• Strategy21
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• s.34
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• pp.149-177
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• 2014

Today distant oceans around the world are regarded as a major 'global commons' for international trade and transportation. Korea is not an exception, because Korea hugely depends on sea lines of communication (SLOC) for supplying vital commodities such as food and energy resource. As a result, assuring a free and safe use of distant ocean beyond territory is also an important agenda for Korea's maritime security. However there are a number of challenges for Korea to enjoy a free and safe use of distant ocean; dangers of regional maritime conflict in East Asia, naval arms race of China and Japan, and concerns on possible decline of U.S naval presence and power projection capabilities. These factors provide a reasonable basis for Republic of Korea Navy (ROKN) to pursue capabilities for major naval operations at distant ocean in a long-term perspective toward the year 2030. The introduction of aircraft carrier and nuclear-powered submarine is a key requirement for achieving this goal. ROKN needs to acquire a 'multi-role strategic landing platform' type of light aircraft carrier, which takes a role to escort naval task force by providing air superiority at distant ocean. Additionally nuclear-powered submarine will offer ROKN a formidable power to carry out offensive missions effectively at distant ocean.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.278-284
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• 2004

The processes for the smelting of a metal product and the solidification of a molten salt were developed respectively to treat the products from the electrochemical reduction process. The method for the separation of a metal product in a magnesia container from the residual. salt and consequent smelting of it to a metal ingot by the multi step heating in vacuum was proposed. The new concept using a dual vessel and a salt valve was also suggested for the solidification of a molten salt into a regular size and shape which is suitable for the transport and measurement. The results obtained in the study will be applied to the design of the hot cell demonstration system of the Advanced Spent Fuel Conditioning Process of KAERI.

• Journal of Energy Engineering
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• v.11 no.2
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• pp.122-129
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• 2002

The analytical models and algorithm of the SPIKE code, which has been developed by KAERI's KALIMER team to investigate the sodium-water reaction phenomena in the liquid metal reactor, were introduced with its verification calculation results. The sodium water reaction of KALIMER IHTS was evaluated. Early stage of the sodium-water reaction consists of wave and mass transfer regimes. The pressure variations were independent of specific design features in the wave transfer regime. However in the mass transfer regime, the pressure variations were strongly dependent on cover gas volume and rupture disk set pressure. The early stage SWR analysis showed that the KALIMER IHTS with an appropriate cover gas volume and rupture disk set pressure had enough margin to its design pressure.

• Nuclear Engineering and Technology
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• v.12 no.2
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• pp.88-98
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• 1980

The process of solidification of a single-phase flowing hot fluid in a cylindrical tube has been investigated analytically and experimentally. A series of tests were performed, using paraffin -wax and Wood's metal as flowing hot fluids. These data verified the existing quasistatic numerical analysis model of freezing process developed at Brookhaven National Laboratory In addition, experimental results provided information regarding the effects of various parameters on the .process of transient flowing and freezing through a vertical channel. The experimental apparatus and techniques are described. Comparison of experimental data with predictions of mathematical models for transient molten fluid displacement are presented in graphical form. In addition, the mathematical model is applied to LMFBR post-accident conditions.

• Proceedings of the Materials Research Society of Korea Conference
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• 2003.03a
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• pp.112-112
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• 2003

최근 자성반도체(diluted magnetic semiconductor; DMS)를 이용한 소자 개발이 가긍해짐에 따라 국내외에서 활발한 연구가 이루어지고 있다. 본 연구실에서는 GaN-단일전구체를 이용하여 상온에서 자기적 특성을 나타내는 p-type GaMnN를 성장시켰다 극한 환경에서의 자성반도체 재료의 물성 변화를 알아보기 위해, 본 연구에서는 세계 최초로 중성자 빔의 조사에 따른 자성반도체의 구조적, 자기적 특성 및 열처리에 따른 특성 변화를 관찰 및 분석하였다. Molecular beam epitaxy(MBE)를 이용하여 Mn cell 온도가 각각 77$0^{\circ}C$, 94$0^{\circ}C$인 GaMnN 박막을 성장시켰다. 성장된 박막 시편에 한국원자력연구소 하나로 HTS공에서 중성자 빔을 각각 20min(4.17$\times$$10^{16}$n/$\textrm{cm}^2$), 24hour(3.0$\times$$10^{18}$n/$\textrm{cm}^2$)씩 조사하였다 중성자 빔을 조사한 시편은 진공분위기 하에서 100$0^{\circ}C$, 30초간 열처리하였다.(rapid thermal annealing;RTA, 승온속도: 8$^{\circ}C$/sec) 중성자 빔을 조사한 GaMnN 박막의 구조적인 특성은 X-ray diffraction(XRD) 측정을 통해 관찰하였고, 박막의 자기적 특성은 superconducting quantum interference device(SQUID)를 통해 측정하였다.

• Nuclear Engineering and Technology
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• v.21 no.4
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• pp.321-331
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• 1989

A bench scale incineration process for the burnable radwaste has been constructed and operated at KAERI as a self-surpported development of incineration technology. The purposes of operating the process are to get experience in incineration, to analyze the characteristics of combustion and to test the performance of off-gas treatment units. Simulated paper and polyethylene wastes were incinerated. Volume reduction ratio and decontamination factor of the process have been determined to observe the economical efficiency and operational capability of the process. A methodology to estimate the acceptance limit of specific activity to an incineration facility by using a decontamination factor and to calculate the volume reduction ratio of the facility is introduced. The acceptance criteria for different radionuclides in the combustible waste at the bench scale incineration process are suggested using this methodology.

• Mineral and Industry
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• v.21 no.1
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• pp.56-66
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• 2008

이 동향자료는 Geoscience Australia에서 2001년 발간한 "Geoscience Australia Mineral Resources Report No.1"과 역시 동 기관에서 2007년 발행한 "Australia's Identified Mineral Resources 2007" 중 일부 내용을 발췌하여 정리 한 것으로서 요약하면 다음과 같다. OECD/NEA와 IAEA(2000)는 세계적으로 분포하는 우라늄 광상유형을 지질학적인 형성환경에 따라 15개 유형으로 분류하였으며 호주에서는 각력복합형, 부정합형, 사암형, 지표형, 변성교대형, 변성형, 화산형, 관입형 및 맥상형이 보고되어 있다. 유형별 자원량은 각력복합형, 부정합형 및 사암형 3개 유형 광상이 약 93%를 차지하며, 각력복합형광상의 자원량이 63%에 달한다. 현재 개발되는 광상은 각력복합형의 올림픽댐 광산, 부정합형인 레인저 광산 및 사암형인 베벌리 광산이다. 호주는 세계 총 우라늄 자원량의 27%를 보유하고 있어 세계 1위를 차지한다. 올림픽댐광상이 항내채광을 하는 우라늄 광산으로서는 세계에서 가장 큰 광상으로서 US$80 이하에서 회수가능한 RAR(적정확정자원량)이 476,000톤이다. 이 자원량은 세계 총 자원량의 18%를 차지하며, 단일 광산으로서는 세계최대규모이다. 2006년 호주의 우라늄 총생산량은 $U_3O_8$ 8,943톤(7,584톤 U)이며 이는 세 광산에서 생산된 양으로서 캐나다에 이어 두 번째로 많은 양(세계 생산량의 19%)이다. 2006년 우라늄 수출량은 $U_3O_8$ 8,660톤(7,344톤 U)이며 수출가는 호주달러 5억2천9백만불에 달한다. 호주는 우라늄 수출국들과 "원자력협력협약"을 맺어 평화적 목적을 위해서만 공급한다는 단서를 달고 있으며 IAEA에 의해 관리/감독되고 있다. 최근 호주 정부는 지구과학연구소에 많은 예산을 투여하여 육상에너지안전대책을 발의하여 자원개발에 요구되는 탐사자료 확보에 주력하고 있다.

• Journal of Radiation Protection and Research
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• v.19 no.2
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• pp.147-156
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• 1994

On-line gamma monitoring system around KAERI-site was set up to monitor the radiation fluctuations in environment. Data on gamma exposure rates measured by the ionication chamber in the monitoring posts are transmitted to a computer of central control station with. radio telemetry transmission modem and monitored in real time. Radio telemetry transmission system is economical and reliable on handling and storing of data. This monitroing system can triger an early warning system in the event of abnormal radiation levels.