• Nuclear Engineering and Technology
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• 제52권11호
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• pp.2460-2470
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• 2020

To study the thermophysical and neutronic properties of thorium-plutonium fuel, a conceptual design of a hybrid facility consisting of a subcritical Th-Pu reactor core and a source of additional D-D neutrons that places on the axis of the core is proposed. The source of such neutrons is a column of high-temperature plasma held in a long magnetic trap for D-D fusionreactions. This article presents computer simulation results of generation of thermonuclear neutrons in the plasma, facility neutronic properties and the evolution of a fuel nuclide composition in the reactor core. Simulations were performed for an axis-symmetric radially profiled reactor core consisting of zones with various nuclear fuel composition. Such reactor core containing a continuously operating stationary D-D neutron source with a yield intensity of Y = 2 × 10¹⁶ neutrons per second can operate as a nuclear hybrid system at its effective coefficient of neutron multiplication 0.95-0.99. Options are proposed for optimizing plasma parameters to increase the neutron yield in order to compensate the effective multiplication factor decreasing and plant power in a long operating cycle (3000-day duration). The obtained simulation results demonstrate the possibility of organizing the stable operation of the proposed hybrid 'fusion-fission' facility.

• 한국정보과학회:학술대회논문집
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• 한국정보과학회 2011년도 한국컴퓨터종합학술대회논문집 Vol.38 No.1(B)
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• pp.258-261
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• 2011

오늘날 에너지를 확보와 관련하여 많은 세계 각국 및 기업에서 다양한 사업과 다양한 실험이 이루어지고 있다. 최근 이와 관련하여 미래의 청정 에너지로 부각되고 있는 핵융합에너지가 관심을 받고 있으며, 국내에서도 많은 연구와 성과가 나타나고 있다. 하지만, 이들 연구성과들을 제대로 관리하여 다른 연구에 재투자할 수 있는 지식관리가 부족한 형편이다. 단순한 지식관리보다는 조직의 비즈니스, 정보, 응용 시스템 및 기반구조에 맞도록 적용하여 적시적소에 이용 가능한 시스템을 구성할 필요가 있다. 따라서 본 연구에서는 핵융합에너지 관련 지식 데이터를 적절하게 관리할 수 있는 개념수준의 포털기반 핵융합 에너지 지식관리시스템의 설계를 제안한다.

• 한국진공학회:학술대회논문집
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• 한국진공학회 2013년도 제44회 동계 정기학술대회 초록집
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• pp.670-670
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• 2013

The concept of a fusion-driven transmutation reactor based on LAR (Low Aspect Ratio) tokamak as a neutron source is studied based on ITER physics and technology. The radial build of transmutation reactor components are self-consistently determined by coupling the systems analysis with radiation transport analysis and an optimal configuration of a transmutation reactor for aspect ratio, A in the range of 1.5 to 2.0 is found. The performance of a transmutation reactor is investigated and shows that a transmutation reactor with a neutron source producing fusion power less than 150 MW can destroy the transuranic actinides contained in the spent fuels produced from more than two 1 GWe PWRs with production of the fission power being greater than 2 GW.

• 한국전기전자재료학회논문지
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• 제20권5호
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• pp.467-470
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• 2007

Application field of neutron beam is very broad including industry, medicine and science. But the research and development and use of neutron beam is restricted within in narrow limits in this country, because neutron beam facility is insufficient - a big research facility of nuclear reactor(HANARO) and some small industrial facilities which use radioisotope neutron source are available. This paper compare and investigate the results of experiment and numerical analysis of the discharge in the spherically convergent beam fusion device which were expected as a portable neutron source. The spherically convergent beam fusion device will offer stability in neutron production, possibility of movement for convenience, low construction cost and higher neutron flux than radioisotope neutron source. The star mode discharge which efficiently generate neutron, were observed at both results.

• 방사성폐기물학회지
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• 제13권2호
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• pp.113-122
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• 2015

원자로의 해체 과정에서 발생되는 방사성 폐기물 내 존재하는 ⁵⁵Fe, ⁶³Ni은 폐기물의 처리방법을 결정하는 데 있어 기초적인 지표로 활용되는 중요한 핵종이다. 하지만 두 핵종은 낮은 방사선량으로 인해 다른 핵종들과의 분리가 필수적이며 또한 시료 매질에서 완전히 추출할 수 있는 전처리가 선행되어야 한다. 따라서 본 연구는 다양한 매질의 원자로 해체 폐기물에 대한 전처리방법의 적용성을 평가하기 위해 NIST SRM 5종 (1646a, 1944, 8704, 2709a, 1633c)에 대하여 왕수, 불산, 과염소산을 각각 이용하는 습식산화법과 alkali-fusion 전처리법에 따른 Iron와 Nickel의 회수율을 비교하였다. 실험 결과 alkali-fusion 방법은 다양한 매질의 인증표준물질에 대해 Iron 95.3∼98.3%, Nickle 86.6∼88.1%의 분석 정확도와 2% 이하의 정밀도를 나타냄으로서 해체폐기물 중 ⁵⁵Fe, ⁶³Ni, 분석에 가장 최적화된 전처리법으로 판단된다.

• Reproductive and Developmental Biology
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• 제28권2호
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• pp.127-132
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• 2004

본 연구는 재래산양의 핵이식을 실시하여 공여세포의 조건, 전기적 세기 및 융합횟수 등이 융합율과 체외발달율에 미치는 영향을 조사하여 최적의 융합조건을 확립하고자 실시하였다. 공여세포는 귀 유래 섬유아세포와 태아 유래 섬유아세포 2종류를 분리 배양하여 사용하였으며, 수핵란의 채취는 성숙한 미경산 재래산양에 과배란을 유기하여 hCG 투여 후 제 35시간째에 외과적인 방법으로 in vivo (체내성숙)난자는 난관을 관류하는 방법으로 회수하고 in vitro (체외성숙)난자는 난포로부터 흡입하여 난포란을 채취하여 약 22시간 체외성숙을 실시하였다. 수핵난자는 난구세포를 제거한 다음 0.05 M sucrose를 처리하여 세포질이 양호하고 극체가 뚜렷하게 보이는 난자만을 선별하여 핵이식을 실시하였다. 핵이식란의 융합은 전기자극방법으로 융합을 실시하였으며, 핵이식 조작 후 약 3시간 동안 전배양을 실시한 다음 활성화를 유도하였다. 복제수정란은 0.8% BSA가 첨가된 mSOF 배양액으로 6∼7일 동안 체외 배양을 실시하였다. 귀 유래 섬유아세포를 공여세포로 사용하였을 때 융합율은 60.4%로서 태아 유래 섬유아세포의 40.3%보다는 높게 나타났다. 분할율에 있어서는 귀 유래 섬유아세포와 태아 유래 섬유아세포가 각각 47.6 및 48.2%로서 차이가 없었다. 2.40∼2.46 ㎸/cm로 전기자극을 주었을 때 융합율은 43.8%로서 1.30∼l.40 ㎸/cm(26.7%)와 2.30∼2.39 ㎸/cm (34.8%)가 높게 나타났으며, 융합이 이루어진 핵이식란의 분할율은 82.9(1.30∼l.40 ㎸/cm), 43.8(2.30∼2.39 ㎸/cm) 및 51.8%(2.40∼2.46 ㎸/cm)로서 전기자극의 세기에 따른 유의적(p＜0.05)인 차이는 없었다. 전기융합을 1회 실시하였을 때 in vivo 난자는 43.5%로서 in vitro 난자의 23.6%보다 유의적으로 높게 나타났으며, 2회 실시하였을 때는 55.7(in vivo) 및 39.2%(in vitro)로 in vivo에서 높게 나타났다. 3회 자극을 주어 전체 융합율은 in vivo가 66.1%로서 in vitro의 52.8%보다는 유의적으로 높게 나타났다.

• Nuclear Engineering and Technology
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• 제41권2호
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• pp.149-154
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• 2009

The microstructure, the corrosion behavior and the oxide properties were examined for Zr-1.5Nb-0.4Sn-0.2Fe-0.1Cr (HANA-4) alloys which were subjected to two different final annealing temperatures: $470^{\circ}C$ and $570^{\circ}C$. HANA-4 was shown to have $\ss$-enriched phase with a bcc crystal structure and Zr(Nb,Fe,Cr)$_2$ with a hcp crystal structure with $\ss$-enriched phase being more frequently observed compared with Zr(Nb,Fe,Cr)$_2$. The corrosion rate of HANA-4 was increased with an increase of the final annealing temperature in the PWR-simulating loop, $360^{\circ}C$ pure water and $400^{\circ}C$ steam conditions, which was correlated well with a reduction in the size of the columnar grains in the oxide/metal interface region. The oxide growth rate of HANA-4 was considerably affected by the alloy microstructure determined by the final annealing temperature.

• Nuclear Engineering and Technology
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• 제37권5호
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• pp.447-456
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• 2005

Laser driven accelerators promise to provide an alternative to conventional accelerator technology. They rely on the excitation of large amplitude density waves in a plasma by the photon pressure of an intense laser. The density oscillations in which electrons and ions are separated, result in extremely large longitudinal electric fields that can be several orders of magnitude larger than those that are used in today's radio-frequency accelerators. Whereas this principle had been demonstrated experimentally for nearly two decades, it was not until 2004 that the production of high quality electron beams around 100 MeV was demonstrated. Analysis, aided by particle-in-cell simulations, as well as experiments with various plasma lengths and densities, indicate that tailoring the length of the accelerator, together with loading of the accelerating structure with beam, are the keys to production of mono-energetic electron beams. Increasing the energy towards a GeV and beyond will require reducing the plasma density and design criteria are discussed for an optimized accelerator module. The current progress and future directions are summarized through comparison with conventional accelerators, highlighting the unique short and long term prospects for intense radiation sources and high energy accelerators based on laser-drivenplasma accelerators.

• 한국자기공명학회논문지
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• 제18권1호
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• pp.15-23
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• 2014

The structural properties and relaxation processes of $MCsSO_4$ (M = Na, K, or Rb) crystals were investigated by measuring the NMR spectra and spin-lattice relaxation rates $1/T_1$ of their $^{23}Na$, $^{39}K$, $^{87}Rb$, and $^{133}Cs$ nuclei. According to the NMR spectra, the $MCsSO_4$ crystals contain two crystallographically inequivalent sites each for the M and Cs ions. Further, the relaxation rates of all these nuclei do not change significantly over the investigated temperature range, indicating that no phase transitions occur in these crystals in this range. The variations in the $1/T_1$ values of the $^{23}Na$, $^{39}K$, $^{87}Rb$, and $^{133}Cs$ nuclei in these three crystals with increasing temperature are approximately proportional to $T^2$, indicating that Raman processes may be responsible for the relaxation. Therefore, for nuclear quadrupole relaxation of the $^{23}Na$, $^{39}K$, $^{87}Rb$, and $^{133}Cs$ nuclei, Raman processes with n = 2 are more effective than direct processes.

• Nuclear Engineering and Technology
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• 제35권6호
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• pp.515-522
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• 2003

Tritium behavior in the solid breeder blanket is one of the key factors in determining tritium self-sufficiency, as well as safety, of fusion reactors. Recently, a model has been developed to describe the tritium behavior in solid breeder material, which can predict the tritium release and inventory in the blanket. However, the model has limitation to account for tritium solubility effects, mainly existing as LiOT, especially inside the $Li_{2}O$ solid breeder. In order to improve the capability of predicting the LiOT precipitation in $Li_{2}O$ solid breeder, a new logic is developed and integrated in the existing tritium release and inventory calculation code. With the logic developed in this work, the code can have capabilities to analyze tritium release and inventories in $Li_{2}O$ under steady and transient conditions. It can be found that tritium inventory as LiOT is an important mechanism under pulsed operation, and the amount of inventory becomes higher as the tritium generation rate increases and the temperature decreases. Also, the temperature limits for the generation of LiOT precipitation are determined. Therefore the developed logic helps understand the tritium transport mechanism in $Li_{2}O$ solid breeder.